WorldWideScience

Sample records for actual safety performance

  1. Food safety performance indicators to benchmark food safety output of food safety management systems.

    Science.gov (United States)

    Jacxsens, L; Uyttendaele, M; Devlieghere, F; Rovira, J; Gomez, S Oses; Luning, P A

    2010-07-31

    There is a need to measure the food safety performance in the agri-food chain without performing actual microbiological analysis. A food safety performance diagnosis, based on seven indicators and corresponding assessment grids have been developed and validated in nine European food businesses. Validation was conducted on the basis of an extensive microbiological assessment scheme (MAS). The assumption behind the food safety performance diagnosis is that food businesses which evaluate the performance of their food safety management system in a more structured way and according to very strict and specific criteria will have a better insight in their actual microbiological food safety performance, because food safety problems will be more systematically detected. The diagnosis can be a useful tool to have a first indication about the microbiological performance of a food safety management system present in a food business. Moreover, the diagnosis can be used in quantitative studies to get insight in the effect of interventions on sector or governmental level. Copyright 2010 Elsevier B.V. All rights reserved.

  2. Food safety performance indicators to benchmark food safety output of food safety management systems

    NARCIS (Netherlands)

    Jacxsens, L.; Uyttendaele, M.; Devlieghere, F.; Rovira, J.; Oses Gomez, S.; Luning, P.A.

    2010-01-01

    There is a need to measure the food safety performance in the agri-food chain without performing actual microbiological analysis. A food safety performance diagnosis, based on seven indicators and corresponding assessment grids have been developed and validated in nine European food businesses.

  3. Determination of Safety Performance Grade of NPP Using Integrated Safety Performance Assessment (ISPA) Program

    International Nuclear Information System (INIS)

    Chung, Dae Wook

    2011-01-01

    Since the beginning of 2000, the safety regulation of nuclear power plant (NPP) has been challenged to be conducted more reasonable, effective and efficient way using risk and performance information. In the United States, USNRC established Reactor Oversight Process (ROP) in 2000 for improving the effectiveness of safety regulation of operating NPPs. The main idea of ROP is to classify the NPPs into 5 categories based on the results of safety performance assessment and to conduct graded regulatory programs according to categorization, which might be interpreted as 'Graded Regulation'. However, the classification of safety performance categories is highly comprehensive and sensitive process so that safety performance assessment program should be prepared in integrated, objective and quantitative manner. Furthermore, the results of assessment should characterize and categorize the actual level of safety performance of specific NPP, integrating all the substantial elements for assessing the safety performance. In consideration of particular regulatory environment in Korea, the integrated safety performance assessment (ISPA) program is being under development for the use in the determination of safety performance grade (SPG) of a NPP. The ISPA program consists of 6 individual assessment programs (4 quantitative and 2 qualitative) which cover the overall safety performance of NPP. Some of the assessment programs which are already implemented are used directly or modified for incorporating risk aspects. The others which are not existing regulatory programs are newly developed. Eventually, all the assessment results from individual assessment programs are produced and integrated to determine the safety performance grade of a specific NPP

  4. Marijuana and actual driving performance

    Science.gov (United States)

    1993-11-01

    This report concerns the effects of marijuana smoking on actual driving performance. It presents the results of one pilot and three actual driving studies. The pilot study's major purpose was to establish the THC dose current marijuana users smoke to...

  5. A concurrent diagnosis of microbiological food safety output and food safety management system performance: Cases from meat processing industries

    NARCIS (Netherlands)

    Luning, P.A.; Jacxsens, L.; Rovira, J.; Oses Gomez, S.; Uyttendaele, M.; Marcelis, W.J.

    2011-01-01

    Stakeholder requirements force companies to analyse their food safety management system (FSMS) performance to improve food safety. Performance is commonly analysed by checking compliance against preset requirements via audits/inspections, or actual food safety (FS) output is analysed by

  6. Pump performance and reliability follow-up by the French Safety Authorities

    International Nuclear Information System (INIS)

    Clausner, J.P.; De La Ronciere, X.; Scott de Martinville, E.; Courbiere, P.

    1990-12-01

    This paper will present, through actual examples, the methodology of the performance and reliability safety-related pumps evaluation applied by the French Safety Authorities and the lessons drawn from this evaluation

  7. Marijuana, alcohol and actual driving performance

    Science.gov (United States)

    1999-07-01

    The purpose of this study was to empirically determine the separate and combined effects of Delta-9-tetrahydrocannabinol (THC) and alcohol on actual driving performance. This was the first study ever in which the drugs' combined effects were measured...

  8. Radiation safety actuality in Republic of Moldova

    International Nuclear Information System (INIS)

    Kuharuk, E.S.

    2011-01-01

    Radioecological monitoring issues and radiation safety are actual in the Republic of Moldova. Japan events show us the possibility of natural disasters. Republic of Moldova is surrounded by 8 NPPs, the closest being at the distance of 160 km. Moldovas territory is in seismic zone where underground earthquake shocks reaches 7 points or more. Thatis why radiation safety and radioecological monitoring is actual in our republic. Traces of Chernobyl were left in Moldovas soils. The fallouts of radio nuclides formed on the soil surfaces in the Republic of Moldova following the Chernobyl Nuclear Power Station Accident have been continuously affected by attacks of both natural and technicaly generated agents since the time of fallout. During the past decade a shift in emphasis has taken place regarding the need for more complete and accurate information on reservoir sedimentation. Classical sedimentation surveys involve repeated field measurement and, therefore, this is probably the most costly and time consuming method. The application of radio nuclides, particularly Cs 137, for water erosion and sedimentation studies in Republic of Moldova has not been attempted so far. This paper presents the results obtained on reservoir sedimentation rates in an area subjected to wide range in land degradation dy sheet-rill erosion. The profil characteristics support the assumption that in most undisturbed sites there is a sharp decline in Cs 137 activity with increasing dept. Such an asymmetrical distribution of the Cs 137 would suggest a standard pattern in the form of a cantilever. If the validity of this assamption is accepted it is possible to define two major types of Cs 137 cantilever distribution: shallow and deep buried cantilever. The main criterion in classifying these pattents lies generally in the shape of Cs 137 depth profile and particularly in burial magnitude of Cs 137 peak derived from Chernobyl. Hills area has been impacted by greatest sendimentation. This regional

  9. Safety performance indicators. Topical issues paper no. 5

    International Nuclear Information System (INIS)

    Dahlgren, K.; Lederman, L.; Szikszai, T.; Palomo, J.

    2001-01-01

    Since its creation the nuclear industry has been struggling with the question of how safe is safe enough. Safety is a common goal to all involved in the design, operation and regulation of a nuclear installation. As a concept safety is not easy to define. However, there is a general understanding of what attributes a nuclear power plant should have in order to operate safely. The challenge lies in measuring the attributes. The new competitive open electricity market, in many countries throughout the world, is increasing the economic pressure on operators to lower operating costs without jeopardizing safety. Challenges are occurring at a rate that is unprecedented in the nuclear industry: competitiveness; downsizing; ageing; policy changes; reorganization; restructuring; mergers; globalization; and takeovers demand increasing attention to the management of safety. There are various means to measure safety performance, some of which are more qualitative in nature and others which through quantitative measures provide the means by which to evaluate performance trends with clear ties to safety. According to their use, indicators are generally considered in two groups: leading or proactive and lagging or reactive indicators. Leading indicators are most useful as a precursor to safety degradation for early management reaction. Lagging indicators are most commonly used to drive plant performance, to monitor and for benchmarking against similar plants. The actual values of the indicators are not intended to be direct measures of safety, although safety performance can be inferred from the results achieved. Each plant needs to determine which indicators best serve its needs. Selected indicators should not be static, but should be adapted to the conditions and performance of the plant, considering the cost-benefit of maintaining each individual indicator. It should be recognized that while indicators provide valuable information in the effective management of plant safety

  10. A study on human performance enhancement plan in maintenance field by survey on actual condition of human performance tools - 15035

    International Nuclear Information System (INIS)

    Park, J.; Jeong, H.; Kim, Y.

    2015-01-01

    Human errors in nuclear power plant are one of the important factors that may cause reactor trip. Most operating companies of nuclear power plants manage human factor systematically through tools like HPES (Human Performance Enhancement), PSR (Periodic Safety Review), OE (Operating Experience), human performance tools, safety culture assessment and CAP (Corrective Action Program). But human factors are managed passively in maintenance field, because maintenance works are carrying out by partner companies. KHNP also contracts the maintenance work to the partner companies, and advise them to use human performance tools. But the actual condition on partner companies has not been surveyed. This paper suggests some plans that can improve human performance by analyzing the opinion of partner company employees about the causes and solutions of human errors, by analyzing utilization of human performance tools and by comparing the results of the partner companies survey with the results of the operating company survey. The survey is conducted to 3 partner companies by similar contents and categories in order to compare partner company with operating company, and the main analysis fields are the following: -1) Level of understanding and utilization of the human performance tools, -2) Difficulties of applying the human performance tools, -3) Level of employee's training (or education) in the use of the human performance tools, and -4) Root causes of human errors and countermeasures. (authors)

  11. Reviewing real-time performance of nuclear reactor safety systems

    International Nuclear Information System (INIS)

    Preckshot, G.G.

    1993-08-01

    The purpose of this paper is to recommend regulatory guidance for reviewers examining real-time performance of computer-based safety systems used in nuclear power plants. Three areas of guidance are covered in this report. The first area covers how to determine if, when, and what prototypes should be required of developers to make a convincing demonstration that specific problems have been solved or that performance goals have been met. The second area has recommendations for timing analyses that will prove that the real-time system will meet its safety-imposed deadlines. The third area has description of means for assessing expected or actual real-time performance before, during, and after development is completed. To ensure that the delivered real-time software product meets performance goals, the paper recommends certain types of code-execution and communications scheduling. Technical background is provided in the appendix on methods of timing analysis, scheduling real-time computations, prototyping, real-time software development approaches, modeling and measurement, and real-time operating systems

  12. Reviewing real-time performance of nuclear reactor safety systems

    Energy Technology Data Exchange (ETDEWEB)

    Preckshot, G.G. [Lawrence Livermore National Lab., CA (United States)

    1993-08-01

    The purpose of this paper is to recommend regulatory guidance for reviewers examining real-time performance of computer-based safety systems used in nuclear power plants. Three areas of guidance are covered in this report. The first area covers how to determine if, when, and what prototypes should be required of developers to make a convincing demonstration that specific problems have been solved or that performance goals have been met. The second area has recommendations for timing analyses that will prove that the real-time system will meet its safety-imposed deadlines. The third area has description of means for assessing expected or actual real-time performance before, during, and after development is completed. To ensure that the delivered real-time software product meets performance goals, the paper recommends certain types of code-execution and communications scheduling. Technical background is provided in the appendix on methods of timing analysis, scheduling real-time computations, prototyping, real-time software development approaches, modeling and measurement, and real-time operating systems.

  13. Risk-based safety performance indicators for nuclear power plants

    International Nuclear Information System (INIS)

    Chakraborty, S.; Prohaska, G.; Flodin, Y.; Grint, G.; Habermacher, H.; Hallman, A.; Isasia, R.; Melendez, E.; Verduras, E.; Karsa, Z.; Khatib-Rahbar, M.; Koeberlein, K.; Schwaeger, C.; Matahri, N.; Moravcik, I.; Tkac, M.; Preston, J.

    2003-01-01

    In a Concerted Action (CA), sponsored by the European Commission within its 5th Framework Program, a consortium of eleven partners from eight countries has reviewed and evaluated the application of Safety Performance Indicators (SPIs), which - in combination with other tools - can be used to monitor and improve the safety of nuclear power plants. The project was aimed at identification of methods that can be used in a risk-informed regulatory system and environment, and to exploit PSA techniques for the development and use of meaningful additional/alternative SPIs. The CA included the review of existing indicator systems, and the collection of information on the experience from indicator systems by means of a specific questionnaire. One of the most important and challenging issues for nuclear plant owners and/or regulators is to recognize early signs of deterioration in safety performance, caused by influences from management, organization and safety culture (MOSC), before actual events and/or mishaps take place. Most of the existing SPIs as proposed by various organizations are considered as 'lagging' indicators, that is, they are expected to show an impact only when a downward trend has already started. Furthermore, most of the available indicators are at a relatively high level, such that they will not provide useful information on fundamental weaknesses causing the problem in the first place. Regulators' and utilities' views on the use of a Safety Performance Indicator System have also been a part of the development of the CA. (author)

  14. Application of Partial Safety Factorsin Building Energy Performance Assessment

    DEFF Research Database (Denmark)

    Brohus, Henrik; Heiselberg, Per; Hesselholt, A.

    2009-01-01

    is evaluated by sensitivity and uncertainty analysis to develop a significantly reduced set of stochastic input parameters. The safety factor approach provides a means of enforcing the maximum allowed energy consumption in the building code by multiplying the maximum limit by a partial safety factor to obtain......In practise many buildings show significant deviation between the predicted annual energy consumption and the actual energy consumption. One of the main reasons for the discrepancy is the difference between the assumptions made during the calculations and the actual conditions including occupants...

  15. Fatigue Performance Assessment of Composite Arch Bridge Suspenders Based on Actual Vehicle Loads

    Directory of Open Access Journals (Sweden)

    Bin Chen

    2015-01-01

    Full Text Available In the through arch bridges, the suspenders are the key components connecting the arch rib and the bridge deck in the middle, and their safety is an increasing focus in the field of bridge engineering. In this study, various vehicle traffic flow parameters are investigated based on the actual vehicle data acquired from the long-term structural health monitoring system of a composite arch bridge. The representative vehicle types and the probability density functions of several parameters are determined, including the gross vehicle weight, axle weight, time headway, and speed. A finite element model of the bridge structure is constructed to determine the influence line of the cable force for various suspenders. A simulated vehicle flow, generated using the Monte Carlo method, is applied on the influence lines of the target suspender to determine the stress process, and then the stress amplitude spectrum is obtained based on the statistical analysis of the stress process using the rainflow counting method. The fatigue performance levels of various suspenders are analyzed according to the Palmgren-Miner linear cumulative damage theory, which helps to manage the safety of the suspenders.

  16. Artificial neural network model for prediction of safety performance indicators goals in nuclear plants

    Energy Technology Data Exchange (ETDEWEB)

    Souto, Kelling C.; Nunes, Wallace W. [Instituto Federal de Educacao, Ciencia e Tecnologia do Rio de Janeiro, Nilopolis, RJ (Brazil). Lab. de Aplicacoes Computacionais; Machado, Marcelo D., E-mail: dornemd@eletronuclear.gov.b [ELETROBRAS Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil). Gerencia de Combustivel Nuclear - GCN.T

    2011-07-01

    Safety performance indicators have been developed to provide a quantitative indication of the performance and safety in various industry sectors. These indexes can provide assess to aspects ranging from production, design, and human performance up to management issues in accordance with policy, objectives and goals of the company. The use of safety performance indicators in nuclear power plants around the world is a reality. However, it is necessary to periodically set goal values. Such goals are targets relating to each of the indicators to be achieved by the plant over a predetermined period of operation. The current process of defining these goals is carried out by experts in a subjective way, based on actual data from the plant, and comparison with global indices. Artificial neural networks are computational techniques that present a mathematical model inspired by the neural structure of intelligent organisms that acquire knowledge through experience. This paper proposes an artificial neural network model aimed at predicting values of goals to be used in the evaluation of safety performance indicators for nuclear power plants. (author)

  17. Artificial neural network model for prediction of safety performance indicators goals in nuclear plants

    International Nuclear Information System (INIS)

    Souto, Kelling C.; Nunes, Wallace W.; Machado, Marcelo D.

    2011-01-01

    Safety performance indicators have been developed to provide a quantitative indication of the performance and safety in various industry sectors. These indexes can provide assess to aspects ranging from production, design, and human performance up to management issues in accordance with policy, objectives and goals of the company. The use of safety performance indicators in nuclear power plants around the world is a reality. However, it is necessary to periodically set goal values. Such goals are targets relating to each of the indicators to be achieved by the plant over a predetermined period of operation. The current process of defining these goals is carried out by experts in a subjective way, based on actual data from the plant, and comparison with global indices. Artificial neural networks are computational techniques that present a mathematical model inspired by the neural structure of intelligent organisms that acquire knowledge through experience. This paper proposes an artificial neural network model aimed at predicting values of goals to be used in the evaluation of safety performance indicators for nuclear power plants. (author)

  18. Safety KPIs - Monitoring of safety performance

    Directory of Open Access Journals (Sweden)

    Andrej Lališ

    2014-09-01

    Full Text Available This paper aims to provide brief overview of aviation safety development focusing on modern trends represented by implementation of Safety Key Performance Indicators. Even though aviation is perceived as safe means of transport, it is still struggling with its complexity given by long-term growth and robustness which it has reached today. Thus nowadays safety issues are much more complex and harder to handle than ever before. We are more and more concerned about organizational factors and control mechanisms which have potential to further increase level of aviation safety. Within this paper we will not only introduce the concept of Key Performance Indicators in area of aviation safety as an efficient control mechanism, but also analyse available legislation and documentation. Finally we will propose complex set of indicators which could be applied to Czech Air Navigation Service Provider.

  19. Safety performance indicators program

    International Nuclear Information System (INIS)

    Vidal, Patricia G.

    2004-01-01

    In 1997 the Nuclear Regulatory Authority (ARN) initiated a program to define and implement a Safety Performance Indicators System for the two operating nuclear power plants, Atucha I and Embalse. The objective of the program was to incorporate a set of safety performance indicators to be used as a new regulatory tool providing an additional view of the operational performance of the nuclear power plants, improving the ability to detect degradation on safety related areas. A set of twenty-four safety performance indicators was developed and improved throughout pilot implementation initiated in July 1998. This paper summarises the program development, the main criteria applied in each stage and the results obtained. (author)

  20. Performance standards of road safety management

    Directory of Open Access Journals (Sweden)

    Čabarkapa Milenko R.

    2016-01-01

    Full Text Available Road safety management controlling means the process of finding out the information whether the road safety is improving in a measure to achieve the objectives. The process of control consists of three basic elements: definition of performances and standards, measurement of current performances and comparison with the set standards, and improvement of current performances, if they deviate from the set standards. The performance standards of road safety management system are focused on a performances measurement, in terms of their design and characteristics, in order to support the performances improvement of road safety system and thus, ultimately, improve the road safety. Defining the performance standards of road safety management system, except that determines the design of the system for performances measurement, directly sets requirements whose fulfillment will produce a road safety improvement. The road safety management system, based on the performance standards of road safety, with a focus on results, will produce the continuous improvement of road safety, achieving the long-term 'vision zero', the philosophy of road safety, that human life and health take priority over mobility and other traffic objectives of the road traffic.

  1. Safety assessment, safety performance indicators at the Paks Nuclear Power Plant

    International Nuclear Information System (INIS)

    Baji, C.; Vamos, G.; Toth, J.

    2001-01-01

    The Paks Nuclear Power Plant has been using different methods of safety assessment (event analysis, self-assessment, probabilistic safety analysis), including performance indicators characterizing both operational and safety performance since the early years of operation of the plant. Regarding the safety performance, the indicators include safety system performance, number of scrams, release of radioactive materials, number of safety significant events, industrial safety indicator, etc. The Paks NPP also reports a set of ten indicators to WANO Performance Indicator Programme which, among others, include safety related indicators as well. However, a more systematic approach to structuring and trending safety indicators is needed so that they can contribute to the enhancement of the operational safety. A more comprehensive set of indicators and a systematic evaluation process was introduced in 1996. The performance indicators framework proposed by the IAEA was adapted to Paks in this year to further improve the process. Safety culture assessment and characterizing safety culture is part of the assessment process. (author)

  2. Toward an understanding of the impact of production pressure on safety performance in construction operations.

    Science.gov (United States)

    Han, Sanguk; Saba, Farzaneh; Lee, Sanghyun; Mohamed, Yasser; Peña-Mora, Feniosky

    2014-07-01

    It is not unusual to observe that actual schedule and quality performances are different from planned performances (e.g., schedule delay and rework) during a construction project. Such differences often result in production pressure (e.g., being pressed to work faster). Previous studies demonstrated that such production pressure negatively affects safety performance. However, the process by which production pressure influences safety performance, and to what extent, has not been fully investigated. As a result, the impact of production pressure has not been incorporated much into safety management in practice. In an effort to address this issue, this paper examines how production pressure relates to safety performance over time by identifying their feedback processes. A conceptual causal loop diagram is created to identify the relationship between schedule and quality performances (e.g., schedule delays and rework) and the components related to a safety program (e.g., workers' perceptions of safety, safety training, safety supervision, and crew size). A case study is then experimentally undertaken to investigate this relationship with accident occurrence with the use of data collected from a construction site; the case study is used to build a System Dynamics (SD) model. The SD model, then, is validated through inequality statistics analysis. Sensitivity analysis and statistical screening techniques further permit an evaluation of the impact of the managerial components on accident occurrence. The results of the case study indicate that schedule delays and rework are the critical factors affecting accident occurrence for the monitored project. Copyright © 2013 Elsevier Ltd. All rights reserved.

  3. Performance of a piezoelectric energy harvester in actual rain

    International Nuclear Information System (INIS)

    Wong, Voon-Kean; Ho, Jee-Hou; Chai, Ai-Bao

    2017-01-01

    When raindrops impact on the surface of a piezoelectric beam, strain energy produced by the impinging raindrop will be converted to harvestable electrical energy by the piezoelectric layers in a cantilever beam. The novelty of this study is to investigate the performance of the harvester in actual rain and provide practical insights on implementation. The influences of rain parameters such as rain rate, rainfall depth, raindrop count, and drop size distribution (DSD) are discussed in this study. The raindrops accumulated on the surface of the piezoelectric beam will form a water layer. It is described using added mass coefficient in this study. In an actual rain experiment, a piezoelectric beam with surface area of 0.0018 m 2 is able to produce 2076 μJ of energy over a duration of 301 min. The energy generation of a raindrop impact piezoelectric energy harvester is highly dependent on the rain rate. Due to the inconsistency of the energy generation, the piezoelectric energy harvester would require an integration of suitable energy storage device for continuous operation. Nevertheless, this work shows the feasibility of harvesting raindrop energy using a piezoelectric beam. - Highlights: • The performance of a piezoelectric rain energy harvester is tested in actual rain. • The energy generation is highly dependent on the rain rate. • Practical insights on the implementation of the harvester are discussed. • A total energy of 2076 μJ is generated over a duration of 301 min.

  4. The antecedents of herbal product actual purchase in Malaysia

    Directory of Open Access Journals (Sweden)

    Sarina Ismail

    2015-08-01

    Full Text Available This study is meant to examine the relationships of several antecedents of actual purchase of herbal product in Malaysia. Actual purchase is considered to have a vital link to a business success. The study identified eight antecedents of consumer actual purchase such as intention, attitude, social influence, product safety and culture belief. A total of 473 respondents (about 82% completed and returned the questionnaire. A seven point Likert scale was used to measure responses. The data were analyzed using Partial Least Squares (PLS path modeling. The path coefficient results supported the direct influence of intention, attitude, social influence and product safety on actual buying. Moreover, the findings reveal that attitude, social influence, product safety, and culture belief also influenced buying intention.

  5. Is road safety management linked to road safety performance?

    Science.gov (United States)

    Papadimitriou, Eleonora; Yannis, George

    2013-10-01

    This research aims to explore the relationship between road safety management and road safety performance at country level. For that purpose, an appropriate theoretical framework is selected, namely the 'SUNflower' pyramid, which describes road safety management systems in terms of a five-level hierarchy: (i) structure and culture, (ii) programmes and measures, (iii) 'intermediate' outcomes'--safety performance indicators (SPIs), (iv) final outcomes--fatalities and injuries, and (v) social costs. For each layer of the pyramid, a composite indicator is implemented, on the basis of data for 30 European countries. Especially as regards road safety management indicators, these are estimated on the basis of Categorical Principal Component Analysis upon the responses of a dedicated road safety management questionnaire, jointly created and dispatched by the ETSC/PIN group and the 'DaCoTA' research project. Then, quasi-Poisson models and Beta regression models are developed for linking road safety management indicators and other indicators (i.e. background characteristics, SPIs) with road safety performance. In this context, different indicators of road safety performance are explored: mortality and fatality rates, percentage reduction in fatalities over a given period, a composite indicator of road safety final outcomes, and a composite indicator of 'intermediate' outcomes (SPIs). The results of the analyses suggest that road safety management can be described on the basis of three composite indicators: "vision and strategy", "budget, evaluation and reporting", and "measurement of road user attitudes and behaviours". Moreover, no direct statistical relationship could be established between road safety management indicators and final outcomes. However, a statistical relationship was found between road safety management and 'intermediate' outcomes, which were in turn found to affect 'final' outcomes, confirming the SUNflower approach on the consecutive effect of each layer

  6. The actual technological progress of NPPs

    International Nuclear Information System (INIS)

    Florescu, Gheorghe; Popa, Adrian; Panaitescu, Valeriu

    2010-01-01

    The actual nuclear R and D issues require new technologies and continuous progress in order to find adequate and effective solutions in sustained and increasing energy demand. The current tendency in energy consumption and occurring of large consumers, especially from Asian countries, imposes finding new means for energy clean, large scale and sustained production. NPPs reliability and availability were permanently monitored and improved; in the mean time the safety of the nuclear energy production was under surveillance. Corresponding development of the new technologies and discovery of improved materials and adequate technological processes offers the possibilities for appropriate implementation and use of them in the NPPs systems configuration and functioning/operation. The modern technologies and scientific discoveries, also the international cooperation, offer the opportunities to brake the actual barriers in order to cumulate and use advanced energy production processes in finding new energy sources and to build improved, reliable and safety power plants. The monitoring systems, intelligent sensors and intelligent SSCs, nanotechnologies and and modern and intelligent materials constitute the main reasons in improvement of the NPPs systems configuration and processes. The paper presents: - The state of the art in the level of actual and useful technologies for nuclear power systems development; - The actual technological limits that need to be over passed for NPPs systems improvements; - The main systems that need improvement and reconfiguration for actual NPPs development and increase in efficient operation, appropriate availability and total safety; - The actual energy production issues; - The key arguments in sustaining the R and D new NPPs systems development; - Future trends in NPPs development; - The limitations in industrial processes knowledge and use. Appropriate R and D in the field of NPPs systems has a specific characteristic that is highlighted in

  7. Study on real working performance and overload safety factor of high arch dam

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    Considering the fact that high arch dams have problems such as complicated stress,high cost,and hazards after being damaged,this paper intends to study the effects of load,material strength,and safety analysis method on dam safety and working performance of arch dams.In this article,the effects of temperature,self weight exaction way and water loading on structure response are first discussed,and a more reasonable way of considering is then put forward.By taking into consideration the mechanical property of materials and comparing the effects of different yield criteria on overloading safety of high arch dams,this paper concludes that brittle characteristics of concrete should be fully considered when conducting safety assessment for high arch dams to avoid overestimating the bearing capacity of the dams.By comparing several typical projects,this paper works out a safety assessment system of multiple safety and relevant engineering analogical analysis methods,which is closer to the actual situation,and thus is able to assess the response of high arch dam structure in a more comprehensive way,elicit the safety coefficients in different situations,and provide a new way of considering the safety assessment of high arch dams.

  8. Consistency across repeated eyewitness interviews: contrasting police detectives' beliefs with actual eyewitness performance.

    Science.gov (United States)

    Krix, Alana C; Sauerland, Melanie; Lorei, Clemens; Rispens, Imke

    2015-01-01

    In the legal system, inconsistencies in eyewitness accounts are often used to discredit witnesses' credibility. This is at odds with research findings showing that witnesses frequently report reminiscent details (details previously unrecalled) at an accuracy rate that is nearly as high as for consistently recalled information. The present study sought to put the validity of beliefs about recall consistency to a test by directly comparing them with actual memory performance in two recall attempts. All participants watched a film of a staged theft. Subsequently, the memory group (N = 84) provided one statement immediately after the film (either with the Self-Administered Interview or free recall) and one after a one-week delay. The estimation group (N = 81) consisting of experienced police detectives estimated the recall performance of the memory group. The results showed that actual recall performance was consistently underestimated. Also, a sharp decline of memory performance between recall attempts was assumed by the estimation group whereas actual accuracy remained stable. While reminiscent details were almost as accurate as consistent details, they were estimated to be much less accurate than consistent information and as inaccurate as direct contradictions. The police detectives expressed a great concern that reminiscence was the result of suggestive external influences. In conclusion, it seems that experienced police detectives hold many implicit beliefs about recall consistency that do not correspond with actual recall performance. Recommendations for police trainings are provided. These aim at fostering a differentiated view on eyewitness performance and the inclusion of more comprehensive classes on human memory structure.

  9. Consistency across Repeated Eyewitness Interviews: Contrasting Police Detectives’ Beliefs with Actual Eyewitness Performance

    Science.gov (United States)

    Krix, Alana C.; Sauerland, Melanie; Lorei, Clemens; Rispens, Imke

    2015-01-01

    In the legal system, inconsistencies in eyewitness accounts are often used to discredit witnesses’ credibility. This is at odds with research findings showing that witnesses frequently report reminiscent details (details previously unrecalled) at an accuracy rate that is nearly as high as for consistently recalled information. The present study sought to put the validity of beliefs about recall consistency to a test by directly comparing them with actual memory performance in two recall attempts. All participants watched a film of a staged theft. Subsequently, the memory group (N = 84) provided one statement immediately after the film (either with the Self-Administered Interview or free recall) and one after a one-week delay. The estimation group (N = 81) consisting of experienced police detectives estimated the recall performance of the memory group. The results showed that actual recall performance was consistently underestimated. Also, a sharp decline of memory performance between recall attempts was assumed by the estimation group whereas actual accuracy remained stable. While reminiscent details were almost as accurate as consistent details, they were estimated to be much less accurate than consistent information and as inaccurate as direct contradictions. The police detectives expressed a great concern that reminiscence was the result of suggestive external influences. In conclusion, it seems that experienced police detectives hold many implicit beliefs about recall consistency that do not correspond with actual recall performance. Recommendations for police trainings are provided. These aim at fostering a differentiated view on eyewitness performance and the inclusion of more comprehensive classes on human memory structure. PMID:25695428

  10. Consistency across repeated eyewitness interviews: contrasting police detectives' beliefs with actual eyewitness performance.

    Directory of Open Access Journals (Sweden)

    Alana C Krix

    Full Text Available In the legal system, inconsistencies in eyewitness accounts are often used to discredit witnesses' credibility. This is at odds with research findings showing that witnesses frequently report reminiscent details (details previously unrecalled at an accuracy rate that is nearly as high as for consistently recalled information. The present study sought to put the validity of beliefs about recall consistency to a test by directly comparing them with actual memory performance in two recall attempts. All participants watched a film of a staged theft. Subsequently, the memory group (N = 84 provided one statement immediately after the film (either with the Self-Administered Interview or free recall and one after a one-week delay. The estimation group (N = 81 consisting of experienced police detectives estimated the recall performance of the memory group. The results showed that actual recall performance was consistently underestimated. Also, a sharp decline of memory performance between recall attempts was assumed by the estimation group whereas actual accuracy remained stable. While reminiscent details were almost as accurate as consistent details, they were estimated to be much less accurate than consistent information and as inaccurate as direct contradictions. The police detectives expressed a great concern that reminiscence was the result of suggestive external influences. In conclusion, it seems that experienced police detectives hold many implicit beliefs about recall consistency that do not correspond with actual recall performance. Recommendations for police trainings are provided. These aim at fostering a differentiated view on eyewitness performance and the inclusion of more comprehensive classes on human memory structure.

  11. Research on mass transfer and actual performance of the membrane regeneration air-conditioning system

    International Nuclear Information System (INIS)

    Li, Xiu-Wei; Zhang, Xiao-Song; Chen, Qing

    2015-01-01

    Highlights: • Experimental research has been made on the membrane air-conditioning system. • We develop mass transfer models for the membrane regeneration process. • The paper exposes the actual performance of the system. • Increase of membrane pairs improves the performance. - Abstract: Absorption air-conditioning system has great advantages in energy conservation and environmental protection. To improve the performance of the traditional system, the membrane regeneration absorption system was proposed. Its COP could approach 6 by regenerating absorbent solution with the ion exchange membranes. However, the theoretical conclusion has not been supported by the experiment. This paper presents the experimental research of the membrane regeneration process. It has investigated the mass transfer process, energy efficiency and actual performance under different working conditions. Based on that, a mass transfer model has been developed and the influences of some key parameters have been exposed. It found the regeneration performance is mainly influenced by the current intensity. The calculation results with the model agree well the experimental data. The actual efficiency was lower than 50%, caused by energy loss in heat and electrochemical reactions. The actual COP is between 1 and 3, lower current intensity and more membrane pairs could improve it.

  12. Indicators of safety culture - selection and utilization of leading safety performance indicators

    Energy Technology Data Exchange (ETDEWEB)

    Reiman, Teemu; Pietikaeinen, Elina (VTT, Technical Research Centre of Finland (Finland))

    2010-03-15

    Safety indicators play a role in providing information on organizational performance, motivating people to work on safety and increasing organizational potential for safety. The aim of this report is to provide an overview on leading safety indicators in the domain of nuclear safety. The report explains the distinction between lead and lag indicators and proposes a framework of three types of safety performance indicators - feedback, monitor and drive indicators. Finally the report provides guidance for nuclear energy organizations for selecting and interpreting safety indicators. It proposes the use of safety culture as a leading safety performance indicator and offers an example list of potential indicators in all three categories. The report concludes that monitor and drive indicators are so called lead indicators. Drive indicators are chosen priority areas of organizational safety activity. They are based on the underlying safety model and potential safety activities and safety policy derived from it. Drive indicators influence control measures that manage the socio technical system; change, maintain, reinforce, or reduce something. Monitor indicators provide a view on the dynamics of the system in question; the activities taking place, abilities, skills and motivation of the personnel, routines and practices - the organizational potential for safety. They also monitor the efficacy of the control measures that are used to manage the socio technical system. Typically the safety performance indicators that are used are lagging (feedback) indicators that measure the outcomes of the socio technical system. Besides feedback indicators, organizations should also acknowledge the important role of monitor and drive indicators in managing safety. The selection and use of safety performance indicators is always based on an understanding (a model) of the socio technical system and safety. The safety model defines what risks are perceived. It is important that the safety

  13. Indicators of safety culture - selection and utilization of leading safety performance indicators

    International Nuclear Information System (INIS)

    Reiman, Teemu; Pietikaeinen, Elina

    2010-03-01

    Safety indicators play a role in providing information on organizational performance, motivating people to work on safety and increasing organizational potential for safety. The aim of this report is to provide an overview on leading safety indicators in the domain of nuclear safety. The report explains the distinction between lead and lag indicators and proposes a framework of three types of safety performance indicators - feedback, monitor and drive indicators. Finally the report provides guidance for nuclear energy organizations for selecting and interpreting safety indicators. It proposes the use of safety culture as a leading safety performance indicator and offers an example list of potential indicators in all three categories. The report concludes that monitor and drive indicators are so called lead indicators. Drive indicators are chosen priority areas of organizational safety activity. They are based on the underlying safety model and potential safety activities and safety policy derived from it. Drive indicators influence control measures that manage the socio technical system; change, maintain, reinforce, or reduce something. Monitor indicators provide a view on the dynamics of the system in question; the activities taking place, abilities, skills and motivation of the personnel, routines and practices - the organizational potential for safety. They also monitor the efficacy of the control measures that are used to manage the socio technical system. Typically the safety performance indicators that are used are lagging (feedback) indicators that measure the outcomes of the socio technical system. Besides feedback indicators, organizations should also acknowledge the important role of monitor and drive indicators in managing safety. The selection and use of safety performance indicators is always based on an understanding (a model) of the socio technical system and safety. The safety model defines what risks are perceived. It is important that the safety

  14. Development of safety performance indicators for HANARO

    International Nuclear Information System (INIS)

    Wu, Jong-Sup; Jung, Hoan-Sung; Ahn, Guk-Hoon; Lee, Kye-Hong; Lim, In-Cheol

    2007-01-01

    The nuclear facilities need an extensive basis for ensuring their safety. An operating organization should conduct its operation and utilization important to the safety in accordance with approved procedures and regulations. The general aims of a management system for nuclear facilities are to improve the safety performance through a planning, control and supervision of safety related activities and to foster a strong safety culture. The effectiveness of a management system can be monitored and measured to confirm the ability of its processes to achieve the intended safety performance by an assessment of the operational performance. The Operational Safety Performance Indicators, also known as SPI, help an organization define and measure a progress with regard to safety activity goals. The elements of a SPI are quantifiable measurements that reflect the critical success factors of an organizational safety. Since 1995, efforts have been directed towards the elaboration of a framework for the establishment of an operational safety performance indicator program in nuclear power plants (NPP). IAEA-TECDOC-1141, 'Operational safety performance indicators for NPP' attempted to provide a frame work for an identification of performance indicators which have a relationship to the desired safety attributes, and therefore, to a safe plant operation. Three key attributes of a smooth operation, an operation with a low risk, and an operation with a positive safety attitude, were recommended, which are associated with a safe operation. Because these attributes cannot be directly measured, an indicator structure is expanded further until a level of easily quantifiable or directly measurable indicators is identified. The intention of this approach is to use quantitative information provided by the specific indicators and to analyze performance trends relative to established goals. The safety activities in HANARO have been continuously conducted to enhance its safe operation. HANARO

  15. Critical review of safety performance metrics

    NARCIS (Netherlands)

    Karanikas, Nektarios

    2016-01-01

    Various tools for safety performance measurement have been introduced in order to fulfil the need for safety monitoring in organisations, which is tightly related to their overall performance and achievement of their business goals. Such tools include accident rates, benchmarking, safety culture and

  16. Making the user visible: analysing irrigation practices and farmers’ logic to explain actual drip irrigation performance

    NARCIS (Netherlands)

    Benouniche, M.; Kuper, M.; Hammani, A.; Boesveld, H.

    2014-01-01

    The actual performance of drip irrigation (irrigation efficiency, distribution uniformity) in the field is often quite different from that obtained in experimental stations. We developed an approach to explain the actual irrigation performance of drip irrigation systems by linking measured

  17. Theoretical Model for the Performance of Liquid Ring Pump Based on the Actual Operating Cycle

    Directory of Open Access Journals (Sweden)

    Si Huang

    2017-01-01

    Full Text Available Liquid ring pump is widely applied in many industry fields due to the advantages of isothermal compression process, simple structure, and liquid-sealing. Based on the actual operating cycle of “suction-compression-discharge-expansion,” a universal theoretical model for performance of liquid ring pump was established in this study, to solve the problem that the theoretical models deviated from the actual performance in operating cycle. With the major geometric parameters and operating conditions of a liquid ring pump, the performance parameters such as the actual capacity for suction and discharge, shaft power, and global efficiency can be conveniently predicted by the proposed theoretical model, without the limitation of empiric range, performance data, or the detailed 3D geometry of pumps. The proposed theoretical model was verified by experimental performances of liquid ring pumps and could provide a feasible tool for the application of liquid ring pump.

  18. 29 CFR 783.33 - Employment “as a seaman” depends on the work actually performed.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 3 2010-07-01 2010-07-01 false Employment âas a seamanâ depends on the work actually... § 783.33 Employment “as a seaman” depends on the work actually performed. Whether an employee is “employed as a seaman”, within the meaning of the Act, depends upon the character of the work he actually...

  19. Indicators to monitor NPP operational safety performance

    International Nuclear Information System (INIS)

    Gomez-Cobo, Ana

    2002-01-01

    Since December 1995 the IAEA activities on safety performance indicators focused on the elaboration of a framework for the establishment of an operational safety performance indicator programme. The development of this framework began with the consideration of the concept of NPP operational safety performance and the identification of operational safety attributes. For each operational safety attribute, overall indicators, envisioned as providing an overall evaluation of relevant aspects of safety performance, were established. Associated with each overall indicator is a level of strategic indicators intended to provide a bridge from overall to specific indicators. Finally each strategic indicator was supported by a set of specific indicators, which represent quantifiable measures of performance. The programme development was enhanced by pilot plant studies, conducted over a 15 month period from January 1998 to March 1999. The result of all this work is compiled in the IAEA-TECDOC-1141, to be published shortly. This paper presents a summary of this IAEA TECDOC. It describes the operational safety performance indicator framework proposed and discusses the results of and lessons learned from the pilot studies. Despite the efforts described, it is clear that additional research is still necessary in areas such as plant-specific adaptation of proposed frameworks in order to suit individual data collection systems and plant characteristics, indicator selection, indicator definition, goal setting, action thresholds, analysis of trends, indicator display systems, analysis of overall safety performance (i.e., aggregation or combination of indicators), safety culture indicators, qualitative indicators, and use of additional indicators to address issues such as industrial safety attitude and performance, staff welfare, and environmental compliance. This is the rationale for a new IAEA Coordinated Research Project on 'Development and application of indicators to monitor NPP

  20. Safety performance indicators for the road network.

    NARCIS (Netherlands)

    Weijermars, W. Gitelman, V. Papadimitriou, E. Lima De & Azevedo, C.

    2010-01-01

    Within the 6th FP European project SafetyNet, a team has worked on the development of Safety Performance Indicators (SPIs) on seven road safety related areas. These SPIs reflect the operational conditions of the road traffic system that influence the system's safety performance. SPIs were developed

  1. Nursing home safety: does financial performance matter?

    Science.gov (United States)

    Oetjen, Reid M; Zhao, Mei; Liu, Darren; Carretta, Henry J

    2011-01-01

    This study examines the relationship between financial performance and selected safety measures of nursing homes in the State of Florida. We used descriptive analysis on a total sample of 1,197. Safety information was from the Online Survey, Certification and Reporting (OSCAR) data of 2003 to 2005, while the financial performance measures were from the Medicare cost reports of 2002 to 2004. Finally, we examined the most frequently cited deficiencies as well as the relationship between financial performance and quality indicators. Nursing homes in the bottom quartile of financial performance perform poorly on most resident-safety measures of care; however, nursing homes in the top two financial categories also experienced a higher number of deficiencies. Nursing homes in the next to lowest quartile of financial performance category best perform on most of these safety measures. The results reinforce the need to monitor nursing home quality and resident safety in US nursing homes, especially among facilities with poor overall financial performance.

  2. Evidence of a logarithmic relationship between motor capacity and actual performance in daily life of the paretic arm following stroke.

    Science.gov (United States)

    Michielsen, Marian E; de Niet, Mark; Ribbers, Gerard M; Stam, Henk J; Bussmann, Johannes B

    2009-04-01

    To examine the associations between actual performance in daily life and function, capacity and self-perceived performance of the paretic upper limb following stroke. Seventeen individuals with stroke. Correlation coefficients between actual performance (measured with the Stroke-Upper Limb Activity Monitor), function (Fugl-Meyer Assessment), capacity (Action Research Arm test) and self-perceived performance (ABILHAND questionnaire). High correlations were found between actual performance and function (r = 0.75; 95% confidence interval (CI): 0.42-0.90), and capacity (r =0.71; 95% CI: 0.35-0.89), whereas a moderate correlation was found between actual performance and self-perceived performance (r = 0.64; 95% CI: 0.21-0.86). For the relationship between actual performance and both function and capacity, logarithmic regression explained more variance than did linear regression. The present study provides first evidence of the existence of a non-linear relationship between actual performance, function and capacity of the paretic upper limb following stroke. The results indicate that function and capacity need to reach a certain threshold-level before actual performance also starts to increase. Because of the small sample size of the present study caution is needed when generalizing these results.

  3. Prospective safety performance evaluation on construction sites.

    Science.gov (United States)

    Wu, Xianguo; Liu, Qian; Zhang, Limao; Skibniewski, Miroslaw J; Wang, Yanhong

    2015-05-01

    This paper presents a systematic Structural Equation Modeling (SEM) based approach for Prospective Safety Performance Evaluation (PSPE) on construction sites, with causal relationships and interactions between enablers and the goals of PSPE taken into account. According to a sample of 450 valid questionnaire surveys from 30 Chinese construction enterprises, a SEM model with 26 items included for PSPE in the context of Chinese construction industry is established and then verified through the goodness-of-fit test. Three typical types of construction enterprises, namely the state-owned enterprise, private enterprise and Sino-foreign joint venture, are selected as samples to measure the level of safety performance given the enterprise scale, ownership and business strategy are different. Results provide a full understanding of safety performance practice in the construction industry, and indicate that the level of overall safety performance situation on working sites is rated at least a level of III (Fair) or above. This phenomenon can be explained that the construction industry has gradually matured with the norms, and construction enterprises should improve the level of safety performance as not to be eliminated from the government-led construction industry. The differences existing in the safety performance practice regarding different construction enterprise categories are compared and analyzed according to evaluation results. This research provides insights into cause-effect relationships among safety performance factors and goals, which, in turn, can facilitate the improvement of high safety performance in the construction industry. Copyright © 2015 Elsevier Ltd. All rights reserved.

  4. Actual imaging time in fetal MRI

    International Nuclear Information System (INIS)

    Brugger, Peter C.; Prayer, Daniela

    2012-01-01

    Objective: Safety issues in magnetic resonance imaging (MRI) are important, especially in fetal MRI. However, since basic data with respect of the effective exposure time in fetal MRI are not available, this study aimed to determine the actual imaging time during a fetal MRI study. Methods: 100 fetal MRI studies of singleton pregnancies performed on a 1.5 T system were analysed with respect to study duration (from starting the survey scan until the end of study), the number of sequences acquired, and the actual imaging time, which was calculated by adding up scan time of each sequence. Furthermore, each sequence type was analysed regarding the number of acquisitions, specific absorption rates (SAR), and duration. Results: Mean study duration was 34.6 min (range: 14–58 min; standard deviation (SD): 9.7 min), the average number of sequences acquired was 26.6 (range: 11–44, SD: 6.6). Actual scan time averaged 11.4 min (range: 4–19 min, SD: 4.0 min). Ultrafast T2-weighted and steady-state free-precession sequences accounted for 62.3% of actual scan time, and were distributed over the whole duration of the study. Conclusion: Actual imaging time only accounts for 33% of total study time and is not continuous. The remaining time is consumed by the preparation phases of the scanner, and is spent with planning sequences and the eventual repositioning of the coil and/or pregnant woman. These data may help to more accurately estimate the exposure to radiofrequency deposition and noise during fetal MRI studies.

  5. Estimations of actual availability

    International Nuclear Information System (INIS)

    Molan, M.; Molan, G.

    2001-01-01

    Adaptation of working environment (social, organizational, physical and physical) should assure higher level of workers' availability and consequently higher level of workers' performance. A special theoretical model for description of connections between environmental factors, human availability and performance was developed and validated. The central part of the model is evaluations of human actual availability in the real working situation or fitness for duties self-estimation. The model was tested in different working environments. On the numerous (2000) workers, standardized values and critical limits for an availability questionnaire were defined. Standardized method was used in identification of the most important impact of environmental factors. Identified problems were eliminated by investments in the organization in modification of selection and training procedures in humanization of working .environment. For workers with behavioural and health problems individual consultancy was offered. The described method is a tool for identification of impacts. In combination with behavioural analyses and mathematical analyses of connections, it offers possibilities to keep adequate level of human availability and fitness for duty in each real working situation. The model should be a tool for achieving adequate level of nuclear safety by keeping the adequate level of workers' availability and fitness for duty. For each individual worker possibility for estimation of level of actual fitness for duty is possible. Effects of prolonged work and additional tasks should be evaluated. Evaluations of health status effects and ageing are possible on the individual level. (author)

  6. A tool to diagnose context riskiness in view of food safety activities and microbiological safety output

    NARCIS (Netherlands)

    Luning, P.A.; Marcelis, W.J.; Boekel, van M.A.J.S.; Rovira, J.; Uyttendaele, M.; Jacxsens, L.

    2011-01-01

    Stakeholders entail increasing demands on food safety management systems (FSMS) stimulating ongoing efforts of companies to progress to more advanced systems. However, the actual microbiological food safety (FS) output is not only a result of the performance of an FSMS, but it also depends on the

  7. Development of safety performance indicators in Japan

    International Nuclear Information System (INIS)

    Ohashi, H.; Tamao, S.; Tanaka, J.; Sawayama, T.

    2001-01-01

    For the purpose of safety regulations of operating nuclear power stations in Japan, the regulatory authorities utilize two types of regulations. One is the direct regulation, such as periodical inspection to inspect the function and performance of equipment important to safety, and the other is the audit type regulation such as preservation inspection to audit the compliance with the safety preservation rules. As performance indicators are expected to be an effective tool to evaluate the activities by audit type regulations, NUPEC is studying a comprehensive set of operational performance indicators to meet the effective evaluation method for the safety preservation activities in the audit type regulations under the frame of current safety regulation system. The study includes the establishment of comprehensive operational performance indicators applicable in Japan, the effective application of performance indicators to the current Japanese regulation, the clarification of the applicable scope of utilization, the possibility of applying the performance indicators. This report describes the present status of our performance indicator studies. After the completion of these studies the regulatory authorities will evaluate if and how the new set of comprehensive performance indicators could be introduced to Japanese regulatory scheme. (author)

  8. Nuclear power performance and safety. V.3. Safety and international co-operation

    International Nuclear Information System (INIS)

    1988-01-01

    The International Conference on Nuclear Power Performance and Safety, organized by the International Atomic Energy Agency, was held at the Austria Centre Vienna (ACV) in Vienna, Austria, from 28 September to 2 October 1987. The objective of the Conference was to promote an exchange of worldwide information on the current trends in the performance and safety of nuclear power and its fuel cycle, and to take a forward look at the expectations and objectives for the 1990s. This objective was accomplished through presentation and discussion of about 200 papers at the Conference. Almost 500 participants and observers from 40 countries and 12 organizations discussed three major questions which were posed as the focus of this Conference: (1) What are the current trends and major issues with regard to performance and safety of nuclear power, the nuclear fuel cycle and radioactive waste management? (2) What steps are being taken or need to be taken to resolve outstanding issues in order to improve the performance of nuclear power with assured safety? (3) What performance objectives and achievements can be anticipated for the 1990s? All presentations of this Conference were divided into six volumes. This is Volume 3 which is devoted to the problems of safety and international cooperation. All presentations of Volume 3 were divided into four sessions as follows: the need for safety in nuclear power programmes (4 papers); international cooperation in nuclear safety (6 papers); technical aspects in plant safety (7 papers); approaches to safety (3 papers). A separate abstract was prepared for each of these 20 papers. Refs, figs and tabs

  9. A Study on the Propulsion Performance in the Actual Sea by means of Full-scale Experiments

    Directory of Open Access Journals (Sweden)

    Jun Kayano

    2013-12-01

    Full Text Available The IMO has adopted Energy Efficiency Design Index (EEDI, Ship Energy Efficiency Management Plan (SEEMP and Energy Efficiency Operational Indicator (EEOI in order to reduce GHG emissions from international shipping. And, the shipping industry is required to develop and improve the energy saving ship operation technologies to meet the above IMO guideline. The weather routing is one of the energy saving navigation technologies and widely adopted by oceangoing merchant ships. The effectiveness of the weather routing mainly depends on the accuracy of weather forecast data and the ship’s propulsion performance prediction. The propulsion performance in the actual sea is usually predicted using the Self Propulsion Factors obtained by model tests. It is necessary to understand the propulsion performance characteristics in the actual sea conditions for the improvement of propulsion performance prediction. From the above points of view, the authors performed full-scale experiments using a training ship in order to investigate the propulsion performance characteristics in the actual sea. This paper describes the analysis results on the characteristics of Power Curves and Self Propulsion Factors under various weather and sea conditions.

  10. Know thyself: misperceptions of actual performance undermine achievement motivation, future performance, and subjective well-being.

    Science.gov (United States)

    Kim, Young-Hoon; Chiu, Chi-Yue; Zou, Zhimin

    2010-09-01

    Contrary to the popular assumption that self-enhancement improves task motivation and future performance, the authors propose that both inflated and deflated self-assessments of performance are linked to an increased likelihood of practicing self-handicapping and having relatively poor performance in future tasks. Consistent with this proposal, we found that irrespective of the level of actual performance, compared with accurate self-assessment, both inflated and deflated self-assessments of task performance are associated with a greater tendency to (a) practice self-handicapping (Study 1: prefer to work under distraction; Study 2: withhold preparatory effort), (b) perform relatively poorly in a subsequent task (Study 3), (c) have relatively low academic achievement (Study 4), and (d) report a relatively low level of subjective well-being (Study 5). The authors discuss these results in terms of their educational implications. (PsycINFO Database Record (c) 2010 APA, all rights reserved).

  11. Communication's Role in Safety Management and Performance for the Road Safety Practices

    OpenAIRE

    Salim Keffane (s)

    2014-01-01

    Communication among organizations could play an important role in increasing road safety. To get in-depth knowledge of its role, this study measured managers' and employees' perceptions of the communication's role on six safety management and performance criteria for road safety practices by conducting a survey using a questionnaire among 165 employees and 135 managers. Path analysis using AMOS-19 software shows that some of the safety management road safety practices have high correlation wi...

  12. Performance of dynamic safety barriers-Structuring, modelling and visualization

    OpenAIRE

    Wikdahl, Olga

    2014-01-01

    The main objective of this master thesis is to discuss performance of dynamic safety barriers. A comprehensive literature review is performed in order to get understanding what dynamic safety barrier is. Three different concepts of dynamic safety barriers based on various meanings of dynamic were derived from the literature review: - dynamic safety barriers related to motion or physical force - dynamic safety barriers as updated barriers from dynamic risk analysis - dynamic safety ...

  13. Actual performance and characteristic of a grid connected photovoltaic power system in the tropics: A short term evaluation

    International Nuclear Information System (INIS)

    Khatib, Tamer; Sopian, Kamaruzzaman; Kazem, Hussein A.

    2013-01-01

    Highlights: • We analyzed an actual performance of grid connected PV system. • We derived accurate models for the system based on the actual performance. • We assist the electricity productively of the proposed system. - Abstract: This paper presents a field operation experience for a grid connected PV system under tropical climate. The system is consisted of a 5 kWp photovoltaic (PV) array and a 6 kW DC/AC inverter. The operation performance data are recorded in order to develop accurate mathematical models for the system as well as to evaluate the productivity of the system. The experiment results show that, the average PV performance (the ratio of the theoretical performance to the actual performance) is 73.12% while the average inverter performance (the ratio of the theoretical inverter efficiency to the actual inverter efficiency) is 98.56%. Moreover, it is found that the daily yield factor of the PV system is 2.51 kW h/kWp day while, the capacity factor is 10.47%. However, it is concluded that the productivity of the system is below the prospected rate and thus, an inspection of the system must be done in order to diagnose the problem of the system’s low productivity. This paper presents worthwhile information for those who are interested in PV system installation in Malaysia and nearby country

  14. A study on method to identify actual causes and conditions of safety rule deviations through analyzing events due to unsafe acts of workers

    International Nuclear Information System (INIS)

    Hirotsu, Yuko; Takeda, Daisuke

    2010-01-01

    The purpose of this study is to establish a method to understand actual causes and condition of intentional deviation from safety rules (including norm and written rules that has developed to anticipate, prevent, detect and recover human errors) in an organization by analyzing events due to unsafe acts of workers (human factor events) and to propose effective measures. Firstly, by reviewing literature regarding safety violations, the following two advantages of investigating actual condition of safety rule deviation through human factor event analysis were extracted, such as (a) being able to clarify relationships between deviations, human errors, and events, and (b) being able to identify specific causal factors that influenced the decision to deviate, including acts of people concerned, problems with rules, task demands, environment and management. Next, through the analysis of human factor event data in accordance with existing human error analysis method on the basis of advantages above, the following three requirements for analyzing event data were extracted, such as (a) gathering information such as rules concerning to the work activities related to the human factor events, and whether there are intentional deviations of the rules, (b) gathering information and identify interrelations among causal factors of the intentional deviations, and (c) gathering information on general condition of deviations and the causal factors. (author)

  15. Incorporating Traffic Control and Safety Hardware Performance Functions into Risk-based Highway Safety Analysis

    Directory of Open Access Journals (Sweden)

    Zongzhi Li

    2017-04-01

    Full Text Available Traffic control and safety hardware such as traffic signs, lighting, signals, pavement markings, guardrails, barriers, and crash cushions form an important and inseparable part of highway infrastructure affecting safety performance. Significant progress has been made in recent decades to develop safety performance functions and crash modification factors for site-specific crash predictions. However, the existing models and methods lack rigorous treatments of safety impacts of time-deteriorating conditions of traffic control and safety hardware. This study introduces a refined method for computing the Safety Index (SI as a means of crash predictions for a highway segment that incorporates traffic control and safety hardware performance functions into the analysis. The proposed method is applied in a computation experiment using five-year data on nearly two hundred rural and urban highway segments. The root-mean square error (RMSE, Chi-square, Spearman’s rank correlation, and Mann-Whitney U tests are employed for validation.

  16. Occupational safety of different industrial sectors in Khartoum State, Sudan. Part 1: Safety performance evaluation.

    Science.gov (United States)

    Zaki, Gehan R; El-Marakby, Fadia A; H Deign El-Nor, Yasser; Nofal, Faten H; Zakaria, Adel M

    2012-12-01

    Safety performance evaluation enables decision makers improve safety acts. In Sudan, accident records, statistics, and safety performance were not evaluated before maintenance of accident records became mandatory in 2005. This study aimed at evaluating and comparing safety performance by accident records among different cities and industrial sectors in Khartoum state, Sudan, during the period from 2005 to 2007. This was a retrospective study, the sample in which represented all industrial enterprises in Khartoum state employing 50 workers or more. All industrial accident records of the Ministry of Manpower and Health and those of different enterprises during the period from 2005 to 2007 were reviewed. The safety performance indicators used within this study were the frequency-severity index (FSI) and fatal and disabling accident frequency rates (DAFR). In Khartoum city, the FSI [0.10 (0.17)] was lower than that in Bahari [0.11 (0.21)] and Omdurman [0.84 (0.34)]. It was the maximum in the chemical sector [0.33 (0.64)] and minimum in the metallurgic sector [0.09 (0.19)]. The highest DAFR was observed in Omdurman [5.6 (3.5)] and in the chemical sector [2.5 (4.0)]. The fatal accident frequency rate in the mechanical and electrical engineering industry was the highest [0.0 (0.69)]. Male workers who were older, divorced, and had lower levels of education had the lowest safety performance indicators. The safety performance of the industrial enterprises in Khartoum city was the best. The safety performance in the chemical sector was the worst with regard to FSI and DAFR. The age, sex, and educational level of injured workers greatly affect safety performance.

  17. US nuclear safety. Review and experience

    International Nuclear Information System (INIS)

    Hanauer, S.H.

    1977-01-01

    The paper deals with the evolution of reactor safety principles, design bases, regulatory requirements, and experience in the United States. Safety concerns have evolved over the years, from reactivity transients and shut-down systems, to blowdowns and containment, to severe design basis accidents and mitigating systems, to the performance of actual materials, systems and humans. The primary safety concerns of one epoch have been superseded in considerable measure by those of later times. Successive plateaus of technical understanding are achieved by solutions being found to earlier problems. Design studies, research, operating experience and regulatory imperatives all contribute to the increased understanding and thus to the safety improvements adopted and accepted. The improvement of safety with time, and the ability of existing reactors to operate safely in the face of new concerns, has confirmed the correctness and usefulness of the defence-in-depth approach and safety margins used in safety design in the United States of America. A regulatory programme such as the one in the United States justifies its great cost by its important contributions to safety. Yet only the designers, constructors and operators of nuclear power plants can actually achieve public safety. The regulatory programme audits, assesses and spot-checks the actual work. Since neither materials nor human beings are flawless, mistakes will be made; that is why defence-in-depth and safety margins are provided. The regulatory programme should enhance safety by decreasing the frequency of uncorrected mistakes. Maintenance of public safety also requires technical and managerial competence and attention in the organizations responsible for nuclear plants as well as regulatory organizations. (author)

  18. Plant safety and performance indicators for regulatory use

    International Nuclear Information System (INIS)

    Ferjancic, M.; Nemec, T.; Cimesa, S.

    2004-01-01

    Slovenian Nuclear Safety Administration (SNSA) supervises nuclear and radiological safety of Krsko NPP. This SNSA supervision is performed through inspections, safety evaluations of plant modifications and event analyses as well as with the safety and performance indicators (SPI) which are a valuable data source for plant safety monitoring. In the past SNSA relied on the SPI provided by Krsko NPP and did not have a set of SPI which would be more appropriate for regulatory use. In 2003 SNSA started with preparation of a new set of SPI which would be more suitable for performing the regulatory oversight of the plant. New internal SNSA procedure which is under preparation will define use and evaluation of SPI and will include definitions for the proposed set of SPI. According to the evaluation of SPI values in comparison with the limiting values and/or trending, the procedure will define SNSA response and actions. (author)

  19. Quantification of the safety status of PWR steam generators

    International Nuclear Information System (INIS)

    Bartonicek, J.; Jonas, O.; Schoeckle, F.

    1996-01-01

    The operational safety of components is affected during the period of operation (e.g., by loads and environmental effects). Additionally, changes in codes and standards can affect the safety margin of a component. In order to determine a quantitative status of the safety, the existing status of the component and the actual knowledge have to be regarded and evaluated. Differences (deficits) with respect to actual demands must be balanced by use of redundant measure to guarantee safety. The procedure is demonstrated using the steam generators of GKN 1 (German nuclear power plant--in operation since 1975) as an example. The existing status of the component regarding design and construction, material, load history (results of monitoring), the results of nondestructive testing and operational experience is determined and related to the actual regulatory and code compliance and to the state of the art in technics. Non-specified loads were measured in operation. Stress and fatigue analysis computations are performed on the base of realistic load patterns (results from monitoring). Thus the safety status can be quantified. Finally the GKN-concept of measures to guarantee the reliability and the safety of the component in future operation is discussed

  20. Stereotactic Target point Verification in Actual Treatment Position of Radiosurgery

    International Nuclear Information System (INIS)

    Yun, Hyong Geun; Lee, Hyun Koo

    1995-01-01

    Purpose : Authors tried to enhance the safety and accuracy of radiosurgery by verifying stereotactic target point in actual treatment position prior to irradiation. Materials and Methods : Before the actual treatment, several sections of anthropomorphic head phantom were used to create a condition of unknown coordinated of the target point. A film was sand witched between the phantom sections and punctured by sharp needle tip. The tip of the needle represented the target point. The head phantom was fixed to the stereotactic ring and CT scan was done with CT localizer attached to the ring. After the CT scanning, the stereotactic coordinates of the target point were determined. The head phantom was secured to accelerator's treatment couch and the movement of laser isocenter to the stereotactic coordinates determined by CT scanning was performed using target positioner. Accelerator's anteroposterior and lateral portal films were taken using angiographic localizers. The stereotactic coordinates determined by analysis of portal films were compared with the stereotactic coordinates previously determined by CT scanning. Following the correction of discrepancy, the head phantom was irradiated using a stereotactic technique of several arcs. After the irradiation, the film which was sand witched between the phantom sections was developed and the degree of coincidence between the center of the radiation distribution with the target point represented by the hole in the film was measured. In the treatment of actual patients, the way of determining the stereotactic coordinates with CT localizers and angiographic localizers between two sets of coordinates, we proceeded to the irradiation of the actual patient. Results : In the phantom study, the agreement between the center of the radiation distribution and the localized target point was very good. By measuring optical density profiles of the sand witched film along axes that intersected the target point, authors could confirm

  1. Job Demands-Control-Support model and employee safety performance.

    Science.gov (United States)

    Turner, Nick; Stride, Chris B; Carter, Angela J; McCaughey, Deirdre; Carroll, Anthony E

    2012-03-01

    The aim of this study was to explore whether work characteristics (job demands, job control, social support) comprising Karasek and Theorell's (1990) Job Demands-Control-Support framework predict employee safety performance (safety compliance and safety participation; Neal and Griffin, 2006). We used cross-sectional data of self-reported work characteristics and employee safety performance from 280 healthcare staff (doctors, nurses, and administrative staff) from Emergency Departments of seven hospitals in the United Kingdom. We analyzed these data using a structural equation model that simultaneously regressed safety compliance and safety participation on the main effects of each of the aforementioned work characteristics, their two-way interactions, and the three-way interaction among them, while controlling for demographic, occupational, and organizational characteristics. Social support was positively related to safety compliance, and both job control and the two-way interaction between job control and social support were positively related to safety participation. How work design is related to employee safety performance remains an important area for research and provides insight into how organizations can improve workplace safety. The current findings emphasize the importance of the co-worker in promoting both safety compliance and safety participation. Crown Copyright © 2011. Published by Elsevier Ltd. All rights reserved.

  2. Operational safety performance of Slovak NPPs in 2005

    International Nuclear Information System (INIS)

    Tomek, J.

    2006-01-01

    In this presentation author presents operational safety performance of Slovak NPPs in 2005. Operation of Slovak NPPs in 2005 was safe and reliable, with: - high level of performance low risk; - minimal impact on the personnel, environment and public; - positive attitude to safety.

  3. An Empirical Analysis of Human Performance and Nuclear Safety Culture

    International Nuclear Information System (INIS)

    Jeffrey Joe; Larry G. Blackwood

    2006-01-01

    The purpose of this analysis, which was conducted for the US Nuclear Regulatory Commission (NRC), was to test whether an empirical connection exists between human performance and nuclear power plant safety culture. This was accomplished through analyzing the relationship between a measure of human performance and a plant's Safety Conscious Work Environment (SCWE). SCWE is an important component of safety culture the NRC has developed, but it is not synonymous with it. SCWE is an environment in which employees are encouraged to raise safety concerns both to their own management and to the NRC without fear of harassment, intimidation, retaliation, or discrimination. Because the relationship between human performance and allegations is intuitively reciprocal and both relationship directions need exploration, two series of analyses were performed. First, human performance data could be indicative of safety culture, so regression analyses were performed using human performance data to predict SCWE. It also is likely that safety culture contributes to human performance issues at a plant, so a second set of regressions were performed using allegations to predict HFIS results

  4. Safety performance of preliminary KALIMER conceptual design

    Energy Technology Data Exchange (ETDEWEB)

    Hahn Dohee; Kim Kyoungdoo; Kwon Youngmin; Chang Wonpyo; Suk Soodong [Korea atomic Energy Resarch Inst., Taejon (Korea)

    1999-07-01

    The Korea Atomic Energy Research Institute (KAERI) is developing KALIMER (Korea Advanced Liquid Metal Reactor), which is a sodium cooled, 150 MWe pool-type reactor. The safety design of KALIMER emphasizes accident prevention by using passive processes, which can be accomplished by the safety design objectives including the utilization of inherent safety features. In order to assess the effectiveness of the inherent safety features in achieving the safety design objectives, a preliminary evaluation of ATWS performance for the KALIMER design has been performed with SSC-K code, which is a modified version of SSC-L code. KAERI's modification of the code includes development of reactivity feedback models for the core and a pool model for KALIMER reactor vessel. This paper describes the models for control rod driveline expansion, gas expansion module and the thermal hydraulic model for reactor pool and the results of preliminary analyses for unprotected loss of flow and loss o heat sink. (author)

  5. Safety performance of preliminary KALIMER conceptual design

    International Nuclear Information System (INIS)

    Hahn Dohee; Kim Kyoungdoo; Kwon Youngmin; Chang Wonpyo; Suk Soodong

    1999-01-01

    The Korea Atomic Energy Research Institute (KAERI) is developing KALIMER (Korea Advanced Liquid Metal Reactor), which is a sodium cooled, 150 MWe pool-type reactor. The safety design of KALIMER emphasizes accident prevention by using passive processes, which can be accomplished by the safety design objectives including the utilization of inherent safety features. In order to assess the effectiveness of the inherent safety features in achieving the safety design objectives, a preliminary evaluation of ATWS performance for the KALIMER design has been performed with SSC-K code, which is a modified version of SSC-L code. KAERI's modification of the code includes development of reactivity feedback models for the core and a pool model for KALIMER reactor vessel. This paper describes the models for control rod driveline expansion, gas expansion module and the thermal hydraulic model for reactor pool and the results of preliminary analyses for unprotected loss of flow and loss o heat sink. (author)

  6. Investigation of ageing status assessment and lifetime evaluation based on actual operation conditions of QNPC NPP

    International Nuclear Information System (INIS)

    Huilie, S.; Chun, G.; Hongyun, L.; Yinqiang, C.; Jun, T.; Wenbing, W.

    2009-01-01

    Qinshan NPP has been successfully operated for over 18 years with 30 year's design life. For 2nd PSR preparation and life extension strategies, a comprehensive status assessment and lifetime evaluation project is performed by NPP and SG research organization (CNPO). Assessment is subjects to main degradation mechanism of SG materials, including tube IGA/IGSCC tube pitting, fatigue of pressure boundary. Based on two primary functions of PWR steam generator, a comprehensive lifetime evaluation system and indicators has been established for keeping structural integrity of SG pressure boundary and thermal output performance. A series of specific assessment activities are implemented for defining actual ageing status and estimating safety and function margin of SG, including SG impurities hideout return analysis, fatigue evaluation of feedwater pipes based thermal stratification number simulation, fatigue evaluation of pressure boundary based on actual transition records, structure integrity assessment for lower chamber with defect, tube fouling analysis and trending etc. Assessment results shows, even extending operation to 50 years, SG would still keep sufficient safety and function margin, SG is not the neck of NPP life extension. (author)

  7. Safety performance indicators used by the Russian Safety Regulatory Authority in its practical activities on nuclear power plant safety regulation

    International Nuclear Information System (INIS)

    Khazanov, A.L.

    2005-01-01

    The Sixth Department of the Nuclear, Industrial and Environmental Regulatory Authority of Russia, Scientific and Engineering Centre for Nuclear and Radiation Safety process, analyse and use the information on nuclear power plants (NPPs) operational experience or NPPs safety improvement. Safety performance indicators (SPIs), derived from processing of information on operational violations and analysis of annual NPP Safety Reports, are used as tools to determination of trends towards changing of characteristics of operational safety, to assess the effectiveness of corrective measures, to monitor and evaluate the current operational safety level of NPPs, to regulate NPP safety. This report includes a list of the basic SPIs, those used by the Russian safety regulatory authority in regulatory activity. Some of them are absent in list of IAEA-TECDOC-1141 ('Operational safety performance indicators for nuclear power plants'). (author)

  8. Actual performance of mechanical ventilators in ICU: a multicentric quality control study.

    Science.gov (United States)

    Govoni, Leonardo; Dellaca', Raffaele L; Peñuelas, Oscar; Bellani, Giacomo; Artigas, Antonio; Ferrer, Miquel; Navajas, Daniel; Pedotti, Antonio; Farré, Ramon

    2012-01-01

    Even if the performance of a given ventilator has been evaluated in the laboratory under very well controlled conditions, inappropriate maintenance and lack of long-term stability and accuracy of the ventilator sensors may lead to ventilation errors in actual clinical practice. The aim of this study was to evaluate the actual performances of ventilators during clinical routines. A resistance (7.69 cmH(2)O/L/s) - elastance (100 mL/cmH(2)O) test lung equipped with pressure, flow, and oxygen concentration sensors was connected to the Y-piece of all the mechanical ventilators available for patients in four intensive care units (ICUs; n = 66). Ventilators were set to volume-controlled ventilation with tidal volume = 600 mL, respiratory rate = 20 breaths/minute, positive end-expiratory pressure (PEEP) = 8 cmH(2)O, and oxygen fraction = 0.5. The signals from the sensors were recorded to compute the ventilation parameters. The average ± standard deviation and range (min-max) of the ventilatory parameters were the following: inspired tidal volume = 607 ± 36 (530-723) mL, expired tidal volume = 608 ± 36 (530-728) mL, peak pressure = 20.8 ± 2.3 (17.2-25.9) cmH(2)O, respiratory rate = 20.09 ± 0.35 (19.5-21.6) breaths/minute, PEEP = 8.43 ± 0.57 (7.26-10.8) cmH(2)O, oxygen fraction = 0.49 ± 0.014 (0.41-0.53). The more error-prone parameters were the ones related to the measure of flow. In several cases, the actual delivered mechanical ventilation was considerably different from the set one, suggesting the need for improving quality control procedures for these machines.

  9. Actual global problems of radiation protection

    International Nuclear Information System (INIS)

    Ninkovic, M.

    1995-01-01

    Personal views on some actual problems in radiation protection are given in this paper. Among these problems are: evolution methodology used in radiation protection regulations; radiation protection, nuclear energy and safety, and new approaches to the process of the hazardous substances management. An interesting fact relating to the X-ray, radiation protection and Nikola Tesla are given also. (author)

  10. Benchmarking Global Food Safety Performances: The Era of Risk Intelligence.

    Science.gov (United States)

    Valleé, Jean-Charles Le; Charlebois, Sylvain

    2015-10-01

    Food safety data segmentation and limitations hamper the world's ability to select, build up, monitor, and evaluate food safety performance. Currently, there is no metric that captures the entire food safety system, and performance data are not collected strategically on a global scale. Therefore, food safety benchmarking is essential not only to help monitor ongoing performance but also to inform continued food safety system design, adoption, and implementation toward more efficient and effective food safety preparedness, responsiveness, and accountability. This comparative study identifies and evaluates common elements among global food safety systems. It provides an overall world ranking of food safety performance for 17 Organisation for Economic Co-Operation and Development (OECD) countries, illustrated by 10 indicators organized across three food safety risk governance domains: risk assessment (chemical risks, microbial risks, and national reporting on food consumption), risk management (national food safety capacities, food recalls, food traceability, and radionuclides standards), and risk communication (allergenic risks, labeling, and public trust). Results show all countries have very high food safety standards, but Canada and Ireland, followed by France, earned excellent grades relative to their peers. However, any subsequent global ranking study should consider the development of survey instruments to gather adequate and comparable national evidence on food safety.

  11. Examination on the actual situation of safety measures for the gas used in semiconductor industry of U. S. A. Amerika no handotai kogyoyo gas no anzen taisaku no jitsujo wo mite

    Energy Technology Data Exchange (ETDEWEB)

    Horiguchi, S [National Inst. of Materials and Chemical Research, Tsukuba (Japan)

    1993-06-15

    In compliance with the request of the Compressed Gas Safety Association of Japan, the visits to the Department of Transportation (DOT), the Occupational Safety and Health Administration, Department of Labor (OSHA), which are the apparatus of government, the Compressed Gas Association (CGA), the makers of gas used in the semiconductor industry, the makers of cylinder cabinet, and the semiconductor manufacturing factories run by Japanese were made by the present authors in order to examine the actual situations of the safety measure to the gas used in semiconductor industry of U.S.A. In this paper, the viewpoints as well as the actual situation relating to the safety measure to the compressed gas in said visited apparatus and enterprises are introduced. Especially, a number of points which should be referred to are indicated that recently in America, the control of the dangerous materials are regulated rigorously due to the environmental problems, and additionally the files of material safety data sheet based on Hazard communication of OSHA are ranged in the passageways for being read freely, the certain safety educations are given to the employees in offices and the visiting traders or marketers concerned as the duty. 1 fig., 2 tabs.

  12. Mixed results in the safety performance of computerized physician order entry.

    Science.gov (United States)

    Metzger, Jane; Welebob, Emily; Bates, David W; Lipsitz, Stuart; Classen, David C

    2010-04-01

    Computerized physician order entry is a required feature for hospitals seeking to demonstrate meaningful use of electronic medical record systems and qualify for federal financial incentives. A national sample of sixty-two hospitals voluntarily used a simulation tool designed to assess how well safety decision support worked when applied to medication orders in computerized order entry. The simulation detected only 53 percent of the medication orders that would have resulted in fatalities and 10-82 percent of the test orders that would have caused serious adverse drug events. It is important to ascertain whether actual implementations of computerized physician order entry are achieving goals such as improved patient safety.

  13. Multilevel Safety Climate and Safety Performance in the Construction Industry: Development and Validation of a Top-Down Mechanism

    Directory of Open Access Journals (Sweden)

    Ran Gao

    2016-11-01

    Full Text Available The character of construction projects exposes front-line workers to dangers and accidents. Safety climate has been confirmed to be a predictor of safety performance in the construction industry. This study aims to explore the underlying mechanisms of the relationship between multilevel safety climate and safety performance. An integrated model was developed to study how particular safety climate factors of one level affect those of other levels, and then affect safety performance from the top down. A questionnaire survey was administered on six construction sites in Vietnam. A total of 1030 valid questionnaires were collected from this survey. Approximately half of the data were used to conduct exploratory factor analysis (EFA and the remaining data were submitted to structural equation modeling (SEM. Top management commitment (TMC and supervisors’ expectation (SE were identified as factors to represent organizational safety climate (OSC and supervisor safety climate (SSC, respectively, and coworkers’ caring and communication (CCC and coworkers’ role models (CRM were identified as factors to denote coworker safety climate (CSC. SEM results show that OSC factor is positively related to SSC factor and CSC factors significantly. SSC factor could partially mediate the relationship between OSC factor and CSC factors, as well as the relationship between OSC factor and safety performance. CSC factors partially mediate the relationship between OSC factor and safety performance, and the relationship between SSC factor and safety performance. The findings imply that a positive safety culture should be established both at the organizational level and the group level. Efforts from all top management, supervisors, and coworkers should be provided to improve safety performance in the construction industry.

  14. Multilevel Safety Climate and Safety Performance in the Construction Industry: Development and Validation of a Top-Down Mechanism.

    Science.gov (United States)

    Gao, Ran; Chan, Albert P C; Utama, Wahyudi P; Zahoor, Hafiz

    2016-11-08

    The character of construction projects exposes front-line workers to dangers and accidents. Safety climate has been confirmed to be a predictor of safety performance in the construction industry. This study aims to explore the underlying mechanisms of the relationship between multilevel safety climate and safety performance. An integrated model was developed to study how particular safety climate factors of one level affect those of other levels, and then affect safety performance from the top down. A questionnaire survey was administered on six construction sites in Vietnam. A total of 1030 valid questionnaires were collected from this survey. Approximately half of the data were used to conduct exploratory factor analysis (EFA) and the remaining data were submitted to structural equation modeling (SEM). Top management commitment (TMC) and supervisors' expectation (SE) were identified as factors to represent organizational safety climate (OSC) and supervisor safety climate (SSC), respectively, and coworkers' caring and communication (CCC) and coworkers' role models (CRM) were identified as factors to denote coworker safety climate (CSC). SEM results show that OSC factor is positively related to SSC factor and CSC factors significantly. SSC factor could partially mediate the relationship between OSC factor and CSC factors, as well as the relationship between OSC factor and safety performance. CSC factors partially mediate the relationship between OSC factor and safety performance, and the relationship between SSC factor and safety performance. The findings imply that a positive safety culture should be established both at the organizational level and the group level. Efforts from all top management, supervisors, and coworkers should be provided to improve safety performance in the construction industry.

  15. Performance scorecard for occupational safety and health management systems

    Directory of Open Access Journals (Sweden)

    Hernâni Veloso Neto

    2012-06-01

    Full Text Available The pro-active and systematic search for best performances should be the two assumptions of any management system, so safety and health management in organizations must also be guided by these same precepts. However, the scientific production evidences that the performance evaluation processes in safety and health continue to be guided, in their essence, by intermittency, reactivity and negativity, which are not consistent with the assumptions referenced above. Therefore, it is essential that health and safety at work management systems (HSW MS are structured from an active and positive viewpoint, focusing on continuous improvement. This implies considering performance evaluation processes that incorporate, on the one hand, monitoring, measuring and verification procedures, and on the other hand, structured matrixes of results that capture the key factors of success, by mobilizing both reactive and proactive indicators. One of the instruments that can fulfill these precepts of health and safety performance evaluation is the SafetyCard, a performance scorecard for HSW MS that we developed and will seek to outline and demonstrate over this paper.

  16. Improvement programme of safety performance indicators (SPIs) in Korea

    International Nuclear Information System (INIS)

    Lee, S.Y.

    2001-01-01

    KINS has developed and used Safety Performance Indicators (SPIs), which are count based and composed of 10 indicators in 8 areas, to monitor the trend of performance of NPPs in Korea since 1997. However, the limited usage of SPIs and the increasing worldwide interest on SPIs became the motivation of the SPI improvement programme in Korea. Korea is planning to establish plant performance evaluation programme through analysis of SPI and result of inspection. The SPI improvement programme is a part of the plant performance evaluation programme and includes study on performance evaluation areas, indicator categories, selection and development of indicators, redefinition of indicators and introduction of graphical display system. The selected performance evaluation areas are general performance, reactor safety and radiation safety. Each area will have categories as sub-areas and a total of six categories are selected. One or two indicators for each category are determined or will be developed to make a set of Safety Performance Indicators. Also, a graphic display system will be introduced to extend the usage of SPIs. (author)

  17. Lean Six-Sigma in Aviation Safety: An implementation guide for measuring aviation system’s safety performance

    OpenAIRE

    Panagopoulos, I.; Atkin, C.J.; Sikora, I.

    2016-01-01

    The paper introduces a conceptual framework that could improve the safety performance measurement process and ultimately the aviation system safety performance. The framework provides an implementation guide on how organisations could design and develop a proactive, measurement tool for assessing and measuring the Acceptable Level of Safety Performance (ALoSP) at sigma (σ) level, a statistical measurement unit. In fact, the methodology adapts and combines quality management tools, a leading i...

  18. Performance Testing Methodology for Safety-Critical Programmable Logic Controller

    International Nuclear Information System (INIS)

    Kim, Chang Ho; Oh, Do Young; Kim, Ji Hyeon; Kim, Sung Ho; Sohn, Se Do

    2009-01-01

    The Programmable Logic Controller (PLC) for use in Nuclear Power Plant safety-related applications is being developed and tested first time in Korea. This safety-related PLC is being developed with requirements of regulatory guideline and industry standards for safety system. To test that the quality of the developed PLC is sufficient to be used in safety critical system, document review and various product testings were performed over the development documents for S/W, H/W, and V/V. This paper provides the performance testing methodology and its effectiveness for PLC platform conducted by KOPEC

  19. EPR dosimetry for actual and suspected overexposures during radiotherapy treatments in Poland

    International Nuclear Information System (INIS)

    Trompier, F.; Sadlo, J.; Michalik, J.; Stachowicz, W.; Mazal, A.; Clairand, I.; Rostkowska, J.; Bulski, W.; Kulakowski, A.; Sluszniak, J.; Gozdz, S.; Wojcik, A.

    2007-01-01

    EPR dosimetry on bone samples was recently used for actual and suspected overexposures during radiotherapy treatments performed in Poland. In 2001 five breast-cancer patients undergoing radiotherapy in the Bialystok Oncology Center, Poland, were overexposed. The overexposure was due to a defective safety interlock and an obsolete safety system of the linear accelerator. For the three most exposed patients, pieces of rib bones removed during surgical reconstruction of the chest wall and skin transplantation allowed an estimation of the accident doses by electron paramagnetic resonance (EPR) spectrometry. The doses delivered during the accident were as high as 60-80 Gy. In 2005, a patient treated in Kielce Holy Cross Cancer Center exhibited similar deep necroses of the chest wall but 6 years following a 'standard upper mantel fields' radiotherapy for Hodgkin's disease. In order to investigate the possible late effect of an overexposure as necrosis origin, the delivered dose was afterward estimated by EPR dosimetry performed on a rib sample

  20. Characterising the Actual Thermal Performance of Buildings: Current Results of Common Exercises Performed in the Framework of the IEA EBC Annex 58-Project

    DEFF Research Database (Denmark)

    Roels, Staf; Bacher, Peder; Bauwens, Geert

    2015-01-01

    Several studies have shown that actual thermal performance of buildings after construction may deviate significantly from that anticipated at design stage. As a result, there is growing interest in full scale testing of components and whole buildings. The IEA EBC Annex 58-project ‘Reliable Building...... Energy Performance Characterisation Based on Full Scale Dynamic Measurements’ is developing the necessary knowledge and tools to achieve reliable in-situ dynamic testing and data analysis methods that can be used to characterise the actual thermal performance and energy efficiency of building components...... and whole buildings. The research within this project is driven by case studies. As a first simple case, an experiment on testing and data analysis is performed on a round robin test box. This test box can be seen as a scale model of a building, built by one of the participants, with fabric properties...

  1. Focus on safety : a comparative analysis of pipeline safety performance 2000-2002

    International Nuclear Information System (INIS)

    2004-01-01

    Canada's National Energy Board (NEB) is responsible for the promotion of safety, environmental protection and economic efficiency in the Canadian public interest in regulating the design, construction, operation and abandonment of interprovincial and international pipelines within Canada. This second annual report provides a review of the safety performance of oil and gas pipeline companies that are regulated by the NEB. The data used to prepare this report originates from two sources: incident reports submitted under the Onshore Pipeline Regulations, 1999, and from information voluntarily provided by pipeline companies under the Safety Performance Indicators (SPI) initiative. Data comparisons with external reference organizations were included. Six key indicators have been identified to provide comprehensive measures of safety performance for pipeline companies: fatalities, ruptures, injury frequencies, liquid releases, gas releases, and unauthorized activities on the right of way. The safety performance of the federally regulated pipeline industry within Canada was satisfactory during this reporting period (2000-2002). The contractor injury frequency rates reported in 2002 were lower than those reported in 2001, and exhibited more consistency with the levels reported in 2000. The NEB is of the opinion that the elevated number of liquid hydrocarbon spills reported in 2000 were a result of elevated construction levels. No fatalities were reported. There was an increase to three from two in the number of ruptures, due in large part to metal loss (corrosion) and cracking, and external interference (third party damage). The number of spills increased to 76 in 2002 from 55 in 2001, which appears to be more in line with industry averages. The volume of hydrocarbon liquid released in 2002 represented one third the volume released in 2001. refs., 5 tabs., 14 figs

  2. A review on the benchmarking concept in Malaysian construction safety performance

    Science.gov (United States)

    Ishak, Nurfadzillah; Azizan, Muhammad Azizi

    2018-02-01

    Construction industry is one of the major industries that propels Malaysia's economy in highly contributes to our nation's GDP growth, yet the high fatality rates on construction sites have caused concern among safety practitioners and the stakeholders. Hence, there is a need of benchmarking in performance of Malaysia's construction industry especially in terms of safety. This concept can create a fertile ground for ideas, but only in a receptive environment, organization that share good practices and compare their safety performance against other benefit most to establish improvement in safety culture. This research was conducted to study the awareness important, evaluate current practice and improvement, and also identify the constraint in implement of benchmarking on safety performance in our industry. Additionally, interviews with construction professionals were come out with different views on this concept. Comparison has been done to show the different understanding of benchmarking approach and how safety performance can be benchmarked. But, it's viewed as one mission, which to evaluate objectives identified through benchmarking that will improve the organization's safety performance. Finally, the expected result from this research is to help Malaysia's construction industry implement best practice in safety performance management through the concept of benchmarking.

  3. Use of safety management practices for improving project performance.

    Science.gov (United States)

    Cheng, Eddie W L; Kelly, Stephen; Ryan, Neal

    2015-01-01

    Although site safety has long been a key research topic in the construction field, there is a lack of literature studying safety management practices (SMPs). The current research, therefore, aims to test the effect of SMPs on project performance. An empirical study was conducted in Hong Kong and the data collected were analysed with multiple regression analysis. Results suggest that 3 of the 15 SMPs, which were 'safety committee at project/site level', 'written safety policy', and 'safety training scheme' explained the variance in project performance significantly. Discussion about the impact of these three SMPs on construction was provided. Assuring safe construction should be an integral part of a construction project plan.

  4. Development of safety performance indicators of regulatory interest (SAFPER) in Pakistan

    International Nuclear Information System (INIS)

    Khatoon, Abida

    2002-01-01

    Safety performance indicators provide a very useful tool for monitoring operational safety of a nuclear power plant. Utilities in many countries have developed plant specific indicators for the assessment of their performance and safety. Regulators can make use of some of these indicators for their regulatory assessment. In addition to these regulatory bodies in some countries have also developed programs for the formulation of safety performance indicators which are used in monitoring operational safety and regulatory decision making. Realizing its usefulness Directorate of Nuclear Safety and Radiation Protection (DNSRP-the regulatory body in Pakistan) has also initiated a country specific program for the development of Safety Performance Indicators (SAFPER) based on data provided by the utility and that collected during the course of regulatory inspections. Selected areas of NPP operation to be monitored are: - Significant events; - Safety systems performance; - Barriers integrity; - Environment protection; - Workers radiation safety; and - Emergency Preparedness. One of the objectives of this program is also to monitor the effectiveness of DNSRP regulatory activities. IAEA framework is taken as one of the bases for our program. Safety performance will be assessed on the basis of Performance Indicators and inspection findings. DNSRP program as shown in Appendix includes the indicators in use and under development. It is felt that the term Safety Performance Indicators may be termed as 'SAFPER Indicators' to be used by the Regulators, as it is clear from this presentation that utility safety performance indicators together with the regulatory effectiveness indicators constitute the measure for the adequate safety to the public and the environment. Additional research is still necessary for: - indicator definition for the proposed and under developed indicators; - data collection systems; - thresholds; - trend analysis; - goal setting (benefit from the trend can be

  5. Safety performance monitoring of autonomous marine systems

    International Nuclear Information System (INIS)

    Thieme, Christoph A.; Utne, Ingrid B.

    2017-01-01

    The marine environment is vast, harsh, and challenging. Unanticipated faults and events might lead to loss of vessels, transported goods, collected scientific data, and business reputation. Hence, systems have to be in place that monitor the safety performance of operation and indicate if it drifts into an intolerable safety level. This article proposes a process for developing safety indicators for the operation of autonomous marine systems (AMS). The condition of safety barriers and resilience engineering form the basis for the development of safety indicators, synthesizing and further adjusting the dual assurance and the resilience based early warning indicator (REWI) approaches. The article locates the process for developing safety indicators in the system life cycle emphasizing a timely implementation of the safety indicators. The resulting safety indicators reflect safety in AMS operation and can assist in planning of operations, in daily operational decision-making, and identification of improvements. Operation of an autonomous underwater vehicle (AUV) exemplifies the process for developing safety indicators and their implementation. The case study shows that the proposed process leads to a comprehensive set of safety indicators. It is expected that application of the resulting safety indicators consequently will contribute to safer operation of current and future AMS. - Highlights: • Process for developing safety indicators for autonomous marine systems. • Safety indicators based on safety barriers and resilience thinking. • Location of the development process in the system lifecycle. • Case study on AUV demonstrating applicability of the process.

  6. Mining Behavior Based Safety Data to Predict Safety Performance

    Energy Technology Data Exchange (ETDEWEB)

    Jeffrey C. Joe

    2010-06-01

    The Idaho National Laboratory (INL) operates a behavior based safety program called Safety Observations Achieve Results (SOAR). This peer-to-peer observation program encourages employees to perform in-field observations of each other's work practices and habits (i.e., behaviors). The underlying premise of conducting these observations is that more serious accidents are prevented from occurring because lower level “at risk” behaviors are identified and corrected before they can propagate into culturally accepted “unsafe” behaviors that result in injuries or fatalities. Although the approach increases employee involvement in safety, the premise of the program has not been subject to sufficient empirical evaluation. The INL now has a significant amount of SOAR data on these lower level “at risk” behaviors. This paper describes the use of data mining techniques to analyze these data to determine whether they can predict if and when a more serious accident will occur.

  7. Evaluating Performance of Safety Management and Occupational Health Using Total Quality Safety Management Model (TQSM

    Directory of Open Access Journals (Sweden)

    E Mohammadfam

    2015-11-01

    Full Text Available Introduction: All organizations, whether public or private, necessitate performance evaluation systems in regard with growth, stability, and development in the competitive fields. One of the existing models for performance evaluation of occupational health and safety management is Total Quality Safety Management model (TQSM. Therefore, the present study aimed to evaluate performance of safety management and occupational health utilizing TQSM model. Methods: In this descriptive-analytic study, the population consisted of 16 individuals, including managers, supervisors, and members of technical protection and work health committee. Then the participants were asked to respond to TQSM questionnaire before and after the implementation of Occupational Health & Safety Advisory Services 18001 (OHSAS18001. Ultimately, the level of each program as well as the TQSM status were determined before and after the implementation of OHSAS18001. Results: The study results showed that the scores obtained by the company before OHSAS 18001’s implementation, was 43.7 out of 312. After implementing OHSAS 18001 in the company and receiving the related certificate, the total score of safety program that company could obtain was 127.12 out of 312 demonstrating a rise of 83.42 scores (26.8%. The paired t-test revealed that mean difference of TQSM scores before and after OHSAS 18001 implementation was proved to be significant (p> 0.05. Conclusion: The study findings demonstrated that TQSM can be regarded as an appropriate model in order to monitor the performance of safety management system and occupational health, since it possesses the ability to quantitatively evaluate the system performance.

  8. Aging evaluation methodology of periodic safety review in Korea

    International Nuclear Information System (INIS)

    Park, Heung-Bae; Jung, Sung-Gyu; Jin, Tae-Eun; Jeong, Ill-Seok

    2002-01-01

    In Korea plant lifetime management (PLIM) study for Kori Unit 1 has been performed since 1993. Meanwhile, periodic safety review (PSR) for all operating nuclear power plants (NPPs) has been started with Kori Unit 1 since 2000 per IAEA recommendation. The evaluation period is 10 years, and safety (evaluation) factors are 11 per IAEA guidelines as represented in table 1. The relationship between PSR factors and PLIM is also represented. Among these factors evaluation of 'management of aging' is one of the most important and difficult factor. This factor is related to 'actual condition of the NPP', 'use of experience from other nuclear NPPs and of research findings', and 'management of aging'. The object of 'management of aging' is to obtain plant safety through identifying actual condition of system, structure and components (SSCs) and evaluating aging phenomena and residual life of SSCs using operating experience and research findings. The paper describes the scope and procedure of valuation of 'management of aging', such as, screening criteria of SSCs, Code and Standards, evaluation of SSCs and safety issues as represented. Evaluating SSCs are determined using final safety analysis report (FSAR) and power unit maintenance system for Nuclear Ver. III (PUMAS/N-III). The screening criteria of SSCs are safety-related items (quality class Q), safety-impact items (quality class T), backfitting rule items (fire protection (10CFR50.48), environmental qualification (10CFR50.49), pressurized thermal shock (10CFR50.61), anticipated transient without scram (10CFR50.62), and station blackout (10CFR50.63)) and regulating authority requiring items[1∼3]. The purpose of review of Code and Standards is identifying actual condition of the NPP and evaluating aging management using effective Code and Standards corresponding to reactor facilities. Code and Standards is composed of regulating laws, FSAR items, administrative actions, regulating actions, agreement items, and other

  9. Operational Safety Performance Indicators and Balanced Scorecard in HANARO

    International Nuclear Information System (INIS)

    Wu, Jong-Sup; Jung, Hoan-Sung; Ahn, Guk-Hoon; Lee, Kye-Hong; Lim, In-Cheol; Kim, Hark-Rho

    2007-01-01

    Research reactors need an extensive basis for ensuring their safety. The importance of a safety management in nuclear facilities and activities has been emphasized. The safety activities in HANARO have been continuously conducted to enhance its safe operation. Last year, HANARO prepared two indicator sets to measure and assess the safety status of the reactor's operation and utilization. One is Safety Performance Indicators (SPI) and the other is Balanced Scorecard (BSC). Through reviewing these indicators, we can obtain the following information; - Plant safety status - Safety parameter trends - Safety information, for example, reactor operation status and radiation safety HANARO will continuously pursue the trends of SPI and BSC

  10. Developing Probabilistic Safety Performance Margins for Unknown and Underappreciated Risks

    Science.gov (United States)

    Benjamin, Allan; Dezfuli, Homayoon; Everett, Chris

    2015-01-01

    Probabilistic safety requirements currently formulated or proposed for space systems, nuclear reactor systems, nuclear weapon systems, and other types of systems that have a low-probability potential for high-consequence accidents depend on showing that the probability of such accidents is below a specified safety threshold or goal. Verification of compliance depends heavily upon synthetic modeling techniques such as PRA. To determine whether or not a system meets its probabilistic requirements, it is necessary to consider whether there are significant risks that are not fully considered in the PRA either because they are not known at the time or because their importance is not fully understood. The ultimate objective is to establish a reasonable margin to account for the difference between known risks and actual risks in attempting to validate compliance with a probabilistic safety threshold or goal. In this paper, we examine data accumulated over the past 60 years from the space program, from nuclear reactor experience, from aircraft systems, and from human reliability experience to formulate guidelines for estimating probabilistic margins to account for risks that are initially unknown or underappreciated. The formulation includes a review of the safety literature to identify the principal causes of such risks.

  11. SGHWR fuel performance, safety and reliability

    International Nuclear Information System (INIS)

    Pickman, D.O.; Inglis, G.H.

    1977-01-01

    The design principles involved in fuel pins and elements need to take account of the sometimes conflicting requirements of performance, safety and reliability. The principal factors involved in this optimisation are discussed and it is shown from fuel irradiation experience in the Winfrith S.G.H.W.R. that the necessary bias toward safety has not resulted in a reliability level lower than that shown by other successful water reactor designs. Reliability has important economic implications and has to be paid for. By a detailed evaluation of S.G.H.W.R. fuel defects it is shown that very few defects can be shown to be related to design, rating or burn-up. This demonstrates that economic aspects have not over-ridden necessary criteria that must be met to achieve the desirable reliability level. It is possible that large-scale experience with S.G.H.W.R. fuel may eventually demonstrate that the balance is too much in favour of reliability and consideration may be given to whether design changes favouring economy could be achieved without compromising safety. The safety criteria applied to S.G.H.W.R. fuel are designed to avoid any possibility of a temperature runaway in any credible accident situation. The philosophy and supporting experimental work programme are outlined and the fuel design features which particularly contribute to maximising safety margins are outlined. Reference is made to new 60 pin fuel element to be used in the commercial S.G.H.W.R.'s and how it compares in design and performance aspects with the 36 pin element that has been used to date in the Winfrith S.G.H.W.R

  12. Road safety performance indicators for the interurban road network.

    NARCIS (Netherlands)

    Yannis, G. Weijermars, W.A.M. Gitelman, V. Vis, M. Chazirisa, A. Papadimitriou, E. & Lima Azevedo, C.

    2013-01-01

    Various road safety performance indicators (SPIs) have been proposed for different road safety research areas, mainly as regards driver behaviour (e.g. seat belt use, alcohol, drugs, etc.) and vehicles (e.g. passive safety); however, no SPIs for the road network and design have been developed. The

  13. Performance Analysis of Multi Stage Safety Injection Tank

    International Nuclear Information System (INIS)

    Shin, Soo Jai; Kim, Young In; Bae, Youngmin; Kang, Han-Ok; Kim, Keung Koo

    2015-01-01

    In general the integral reactor has such characteristics, the integral reactor requires a high flow rate of coolant safety injection at the initial stage of the accident in which the core level is relatively fast decreased, A medium flow rate of coolant safety injection at the early and middle stages of the accident in which the coolant discharge flow rate is relatively large due to a high internal pressure of the reactor vessel, and a low flow rate of coolant safety injection is required at the middle and late stages of the accident in which the coolant discharge flow rate is greatly reduced due to a decreased pressure of the reactor vessel. It is noted that a high flow rate of the integral reactor is quite smaller compared to a flow rate required in the commercial loop type reactor. However, a nitrogen pressurized safety injection tank has been typically designed to quickly inject a high flow rate of coolant when the internal pressure of the reactor vessel is rapidly decreased, and a core makeup tank has been designed to safely inject at a single mode flow rate due to a gravitational head of water subsequent to making a pressure balance between the reactor vessel and core makeup tank. As a result, in order to compensate such a disadvantage, various type systems are used in a complicated manner in a reactor according to the required characteristic of safety injection during an accident. In the present study, we have investigated numerically the performance of the multi stage safety injection tank. A parameter study has performed to understand the characteristics of the multi stage safety injection tank. The performance of the multi stage safety injection tank has been investigated numerically. When an accident occurs, the coolant in the multi stage safety injection tank is injected into a reactor vessel by a gravitational head of water subsequent to making a pressure balance between the reactor and tank. At the early stages of the accident, the high flow rate of

  14. Performance Analysis of Multi Stage Safety Injection Tank

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Soo Jai; Kim, Young In; Bae, Youngmin; Kang, Han-Ok; Kim, Keung Koo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    In general the integral reactor has such characteristics, the integral reactor requires a high flow rate of coolant safety injection at the initial stage of the accident in which the core level is relatively fast decreased, A medium flow rate of coolant safety injection at the early and middle stages of the accident in which the coolant discharge flow rate is relatively large due to a high internal pressure of the reactor vessel, and a low flow rate of coolant safety injection is required at the middle and late stages of the accident in which the coolant discharge flow rate is greatly reduced due to a decreased pressure of the reactor vessel. It is noted that a high flow rate of the integral reactor is quite smaller compared to a flow rate required in the commercial loop type reactor. However, a nitrogen pressurized safety injection tank has been typically designed to quickly inject a high flow rate of coolant when the internal pressure of the reactor vessel is rapidly decreased, and a core makeup tank has been designed to safely inject at a single mode flow rate due to a gravitational head of water subsequent to making a pressure balance between the reactor vessel and core makeup tank. As a result, in order to compensate such a disadvantage, various type systems are used in a complicated manner in a reactor according to the required characteristic of safety injection during an accident. In the present study, we have investigated numerically the performance of the multi stage safety injection tank. A parameter study has performed to understand the characteristics of the multi stage safety injection tank. The performance of the multi stage safety injection tank has been investigated numerically. When an accident occurs, the coolant in the multi stage safety injection tank is injected into a reactor vessel by a gravitational head of water subsequent to making a pressure balance between the reactor and tank. At the early stages of the accident, the high flow rate of

  15. Approach to uncertainty evaluation for safety analysis

    International Nuclear Information System (INIS)

    Ogura, Katsunori

    2005-01-01

    Nuclear power plant safety used to be verified and confirmed through accident simulations using computer codes generally because it is very difficult to perform integrated experiments or tests for the verification and validation of the plant safety due to radioactive consequence, cost, and scaling to the actual plant. Traditionally the plant safety had been secured owing to the sufficient safety margin through the conservative assumptions and models to be applied to those simulations. Meanwhile the best-estimate analysis based on the realistic assumptions and models in support of the accumulated insights could be performed recently, inducing the reduction of safety margin in the analysis results and the increase of necessity to evaluate the reliability or uncertainty of the analysis results. This paper introduces an approach to evaluate the uncertainty of accident simulation and its results. (Note: This research had been done not in the Japan Nuclear Energy Safety Organization but in the Tokyo Institute of Technology.) (author)

  16. Managing patient safety through NPSGs and employee performance.

    Science.gov (United States)

    Adair, Liberty

    2010-01-01

    Patient safety can only exist in a culture of patient safety, which implies it is a value perceived by all. Culture predicts safety outcomes and leadership predicts the culture. Leaders are obligated to continually mitigate hazard and take action consciously. Healthcare workers should focus on preventing and reporting mistakes with the National Patient Safety Goals (NPSGs) in mind. These include: accuracy of patient identification, effectiveness of communication among caregivers, improving safety of medications, reducing infections, reducing risk of falls, and encouraging patients to be involved in care. Poor performers and reckless behavior need to be mitigated. If employees recognize their roles in the process, feel empowered,and have appropriate tools, resources,and data to implement solutions, errors can be avoided and patient safety becomes paramount.

  17. A road safety performance indicator for vehicle fleet compatibility.

    Science.gov (United States)

    Christoph, Michiel; Vis, Martijn Alexander; Rackliff, Lucy; Stipdonk, Henk

    2013-11-01

    This paper discusses the development and the application of a safety performance indicator which measures the intrinsic safety of a country's vehicle fleet related to fleet composition. The indicator takes into account both the 'relative severity' of individual collisions between different vehicle types, and the share of those vehicle types within a country's fleet. The relative severity is a measure for the personal damage that can be expected from a collision between two vehicles of any type, relative to that of a collision between passenger cars. It is shown how this number can be calculated using vehicle mass only. A sensitivity analysis is performed to study the dependence of the indicator on parameter values and basic assumptions made. The indicator is easy to apply and satisfies the requirements for appropriate safety performance indicators. It was developed in such a way that it specifically scores the intrinsic safety of a fleet due to its composition, without being influenced by other factors, like helmet wearing. For the sake of simplicity, and since the required data is available throughout Europe, the indicator was applied to the relative share of three of the main vehicle types: passenger cars, heavy goods vehicles and motorcycles. Using the vehicle fleet data from 13EU Member States and Norway, the indicator was used to rank the countries' safety performance. The UK was found to perform best in terms of its fleet composition (value is 1.07), while Greece has the worst performance with the highest indicator value (1.41). Copyright © 2013 Elsevier Ltd. All rights reserved.

  18. Operational safety performance indicators for nuclear power plants

    International Nuclear Information System (INIS)

    2000-05-01

    Since the late 1980s, the IAEA has been actively sponsoring work in the area of indicators to monitor nuclear power plant (NPP) operational safety performance. The early activities were mainly focused on exchanging ideas and good practices in the development and use of these indicators at nuclear power plants. Since 1995 efforts have been directed towards the elaboration of a framework for the establishment of an operational safety performance indicator programme. The result of this work, compiled in this publication, is intended to assist NPPs in developing and implementing a monitoring programme, without overlooking the critical aspects related to operational safety performance. The framework proposed in this report was presented at two IAEA workshops on operational safety performance indicators held in Ljubljana, Slovenia, in September 1998 and at the Daya Bay NPP, Szenzhen, China, in December 1998. During these two workshops, the participants discussed and brainstormed on the indicator framework presented. These working sessions provided very useful insights and ideas which where used for the enhancement of the framework proposed. The IAEA is acknowledging the support and contribution of all the participants in these two activities. The programme development was enhanced by pilot plant studies. Four plants from different countries with different designs participated in this study with the objective of testing the applicability, usefulness and viability of this approach

  19. SAFETY PERFORMANCE OF SUBCONTRACTORS IN THE PALESTINIAN CONSTRUCTION INDUSTRY

    Directory of Open Access Journals (Sweden)

    Adnan Enshassi

    2008-06-01

    Full Text Available Subcontractors perform most of the construction works and their effect on industry are apparent in different activities of construction. Therefore, subcontractors need more attention from government and contractors union. The aim of this paper is to identify, evaluate, and rank factors that influence safety performance of subcontractors in the Gaza Strip (Palestine according to their relative importance. The study concluded that reported accident rates will decrease among subcontractors and their workers if new workers are trained well in the work site and they are informed about dangerous places, and if a workable safety plan is well preplanned. The results also showed that reported accident rates increased among subcontractors when using old, unsafe equipment and due to the complexity or difficulty in the construction sites features. Owners and general contractors need to stipulate strict clauses for safety in the contract for improving safety record of subcontractors. Construction workers must receive proper job related safety and health training with a safety logbook. It is recommended that the subcontractors and workers should attend continuing safety programs on regular basis as part of their perquisite to work in construction sites.

  20. Safety performance evaluation using proactive indicators in a selected industry

    Directory of Open Access Journals (Sweden)

    Abolfazl Barkhordari

    2015-03-01

    Full Text Available Background & Objectives: Quality and effectiveness of safety systems are critical factors in achieving their goals. This study was aimed to represent a method for performance evaluation of safety systems by proactive indicators using different updated models in the field of safety which will be tested in a selected industry. Methods: This study is a cross-sectional study. Proactive indicators used in this study were: Unsafe acts rate, Safety Climate, Accident Proneness, and Near-miss incident rate. The number of in 1473 safety climate questionnaires and 543 Accident Proneness questionnaires was completed. Results: The minimum and maximum safety climate score were 56.88 and 58.2, respectively, and the minimum and maximum scores of Accident Proneness were 98.2 and 140.7, respectively. The maximum number of Near-miss incident rate were 408 and the minimum of that was 196. The maximum number of unsafe acts rate was 43.8 percent and the minimum of that was 27.2 percent. In nine dimensions of Safety climate the eighth dimension (personal perception of risk with the score of 4.07 has the lowest score and the fourth (laws and safety regulations dimension with 8.05 has the highest score. According to expert opinions, the most important indicator in the assessment of safety performance was unsafe acts rate, while near-miss incident rate was the least important one. Conclusion: The results of this survey reveal that using proactive (Prospective indicators could be an appropriate method in organizations safety performance evaluation.

  1. Indicators to monitor NPP safety performance. Working material

    International Nuclear Information System (INIS)

    1997-01-01

    Numerical indicators to monitor safety status and overall safety performance of nuclear power plants (NPPs) are used by operators and some regulators worldwide. During the last few years, the IAEA, through Technical Committee Meetings and Consultants' Meetings has worked on this area. This report presents a framework for nuclear power plant safety performance indicators that was developed during two consultant meetings held at the IAEA headquarters in Vienna in December 1995 and November 1996. Annex 2 on risk based indicators was prepared during a consultants' meeting held in Vienna in July 1996. An additional outcome from these activities, was the recommendation that the IAEA conduce pilot exercises at several nuclear power plants that might be interested to participate, in order to test the validity of the concept and its usefulness. 6 figs

  2. Core size effects on safety performances of LMRs

    Energy Technology Data Exchange (ETDEWEB)

    Na, Byung Chan; Hahn, Do Hee [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1998-12-31

    An oxide fuel small size core (1200 MWt) was analyzed in comparison with a large size core (3600 MWt) in order to evaluate the size effects on transient safety performances of liquid-metal reactors (LMRs). In the first part of the study, main static safety parameters (i.e., Doppler coefficient, sodium void effect, etc.) of the two cores were characterized, and the second part of the study was focused on the dynamic behavior of the cores in two representative transient events: the unprotected loss-of-flow (ULOF) and the unprotected transient overpower (UTOP). Margins to fuel melting and sodium boiling have been evaluated for these representative transients. Results show that the small core has a generally better or equivalent level of safety performances during these events. 6 refs., 4 figs., 2 tabs. (Author)

  3. Core size effects on safety performances of LMRs

    Energy Technology Data Exchange (ETDEWEB)

    Na, Byung Chan; Hahn, Do Hee [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    An oxide fuel small size core (1200 MWt) was analyzed in comparison with a large size core (3600 MWt) in order to evaluate the size effects on transient safety performances of liquid-metal reactors (LMRs). In the first part of the study, main static safety parameters (i.e., Doppler coefficient, sodium void effect, etc.) of the two cores were characterized, and the second part of the study was focused on the dynamic behavior of the cores in two representative transient events: the unprotected loss-of-flow (ULOF) and the unprotected transient overpower (UTOP). Margins to fuel melting and sodium boiling have been evaluated for these representative transients. Results show that the small core has a generally better or equivalent level of safety performances during these events. 6 refs., 4 figs., 2 tabs. (Author)

  4. The spin project: safety and performance indicators in different time frames

    International Nuclear Information System (INIS)

    Storck, R.; Becker, D.A.

    2002-01-01

    Safety and performance indicators have been under discussion for many years in several countries and international organisations. If those indicators refer to the long term safety of the total disposal system, they are often called safety indicators. If they refer to the performance of subsystems or the total system from a more technical point of view, they are sometimes called performance indicators. The need for indicators other than dose rates derives e.g. from the long time frames involved in safety assessments of waste disposal systems and the increasing uncertainty in dose rate calculations over time due to uncertainty in evolution of the surface environment and of behaviour of man. Before introducing additional indicators into a safety case of a potential repository site, the applicability and usefulness of different indicators have to be investigated and evaluated. The systematic analysis and testing of safety and performance indicators for use in different time horizons after closure of the disposal facility is the task of the SPIN project. This is done by re-calculating four recent studies concerning repository projects in granite formations. (authors)

  5. Predicting psychopharmacological drug effects on actual driving performance (SDLP) from psychometric tests measuring driving-related skills

    OpenAIRE

    Verster, Joris C.; Roth, Thomas

    2011-01-01

    Rationale There are various methods to examine driving ability. Comparisons between these methods and their relationship with actual on-road driving is often not determined. Objective The objective of this study was to determine whether laboratory tests measuring driving-related skills could adequately predict on-the-road driving performance during normal traffic. Methods Ninety-six healthy volunteers performed a standardized on-the-road driving test. Subjects were instructed to drive with a ...

  6. Benchmarking road safety performance: Identifying a meaningful reference (best-in-class).

    Science.gov (United States)

    Chen, Faan; Wu, Jiaorong; Chen, Xiaohong; Wang, Jianjun; Wang, Di

    2016-01-01

    For road safety improvement, comparing and benchmarking performance are widely advocated as the emerging and preferred approaches. However, there is currently no universally agreed upon approach for the process of road safety benchmarking, and performing the practice successfully is by no means easy. This is especially true for the two core activities of which: (1) developing a set of road safety performance indicators (SPIs) and combining them into a composite index; and (2) identifying a meaningful reference (best-in-class), one which has already obtained outstanding road safety practices. To this end, a scientific technique that can combine the multi-dimensional safety performance indicators (SPIs) into an overall index, and subsequently can identify the 'best-in-class' is urgently required. In this paper, the Entropy-embedded RSR (Rank-sum ratio), an innovative, scientific and systematic methodology is investigated with the aim of conducting the above two core tasks in an integrative and concise procedure, more specifically in a 'one-stop' way. Using a combination of results from other methods (e.g. the SUNflower approach) and other measures (e.g. Human Development Index) as a relevant reference, a given set of European countries are robustly ranked and grouped into several classes based on the composite Road Safety Index. Within each class the 'best-in-class' is then identified. By benchmarking road safety performance, the results serve to promote best practice, encourage the adoption of successful road safety strategies and measures and, more importantly, inspire the kind of political leadership needed to create a road transport system that maximizes safety. Copyright © 2015 Elsevier Ltd. All rights reserved.

  7. Methods and Effects of Safety Enhancement in Korean PSR

    International Nuclear Information System (INIS)

    Kim, Young Gab; Park, Jong Woon

    2009-01-01

    Periodic Safety Review (PSR) is a comprehensive study on a nuclear power plant safety, taking into account aspects such as operational history, ageing, safety analyses and advances in code and standards since the time of construction. In Korea, PSRs have been performed for 20 units and have been effectively used to obtain an overall view of actual plant safety to determine reasonable and practical modifications that should be made in order to obtain a higher level of safety approaching that of modern plants. Among many safety enhancements achieved from Korean PSRs, new safety analyses are the important methods to confirm plant safety by increasing safety margin for specific safety issues. Methods and effects of safety enhancements applied in Korean PSRs are reviewed in this paper in light of new safety analyses to obtain additional safety margins

  8. Seismic Safety Guide

    International Nuclear Information System (INIS)

    Eagling, D.G.

    1985-01-01

    The Seismic Safety Guide provides facilities managers with practical guidelines for administering a comprehensive earthquake safety program. Most facilities managers, unfamiliar with earthquake engineering, tend to look for answers in techniques more sophisticated than required to solve the actual problems in earthquake safety. Often the approach to solutions to these problems is so academic, legalistic, and financially overwhelming that mitigation of actual seismic hazards simply does not get done in a timely, cost-effective way. The objective of the Guide is to provide practical advice about earthquake safety so that managers and engineers can get the job done without falling into common pitfalls, prolonged diagnosis, and unnecessary costs. It is comprehensive with respect to earthquakes in that it covers the most important aspects of natural hazards, site planning, rehabilitation of existing buildings, design of new facilities, operational safety, emergency planning, non-structural elements, life lines, and risk management. 5 references

  9. 2011 Annual Criticality Safety Program Performance Summary

    Energy Technology Data Exchange (ETDEWEB)

    Andrea Hoffman

    2011-12-01

    The 2011 review of the INL Criticality Safety Program has determined that the program is robust and effective. The review was prepared for, and fulfills Contract Data Requirements List (CDRL) item H.20, 'Annual Criticality Safety Program performance summary that includes the status of assessments, issues, corrective actions, infractions, requirements management, training, and programmatic support.' This performance summary addresses the status of these important elements of the INL Criticality Safety Program. Assessments - Assessments in 2011 were planned and scheduled. The scheduled assessments included a Criticality Safety Program Effectiveness Review, Criticality Control Area Inspections, a Protection of Controlled Unclassified Information Inspection, an Assessment of Criticality Safety SQA, and this management assessment of the Criticality Safety Program. All of the assessments were completed with the exception of the 'Effectiveness Review' for SSPSF, which was delayed due to emerging work. Although minor issues were identified in the assessments, no issues or combination of issues indicated that the INL Criticality Safety Program was ineffective. The identification of issues demonstrates the importance of an assessment program to the overall health and effectiveness of the INL Criticality Safety Program. Issues and Corrective Actions - There are relatively few criticality safety related issues in the Laboratory ICAMS system. Most were identified by Criticality Safety Program assessments. No issues indicate ineffectiveness in the INL Criticality Safety Program. All of the issues are being worked and there are no imminent criticality concerns. Infractions - There was one criticality safety related violation in 2011. On January 18, 2011, it was discovered that a fuel plate bundle in the Nuclear Materials Inspection and Storage (NMIS) facility exceeded the fissionable mass limit, resulting in a technical safety requirement (TSR) violation. The

  10. The safety performance management system: A tool for diagnosis, intervention and measurement

    International Nuclear Information System (INIS)

    Haber, S.B.; Shurberg, D.A.

    2002-01-01

    Many organizations depend on human performance to avoid incidents involving significant adverse consequences. Such organizations are typically termed high reliability organizations (HROs). While heavy emphasis has been placed on designing system hardware and software to intercept and mitigate events that could cause adverse consequences, dealing with the design of the human component has proven to be more complicated. Examination of various safety-related incidents makes it clear that human performance, and in particular organizational processes, plays a dominant role. The human errors are of various origins and are typically part of larger organizational processes that encourage unsafe acts that ultimately produce system failures. It is generally postulated that without an effective organizational safety culture, a safe working environment is impossible. While many different perspectives exist from which safety issues might be addressed, a method that allows the quantitative measurement of organizational processes deemed to impact overall safety performance is considered useful to understand the potential for future inadequate safety performance. This paper describes the Safety Performance Management System, a method useful for diagnosis, subsequent intervention and follow-on measurement. Implications for use of this method are presented and the concluding discussion includes insights regarding the general application of the method to improved facility safety performance. (author)

  11. Safety system function trend indicator: Theory and test application

    International Nuclear Information System (INIS)

    Azarm, M.A.; Carbonaro, J.F.; Boccio, J.L.; Vesely, W.E.

    1989-01-01

    The purpose of this paper is to summarize research conducted on the development and validation of quantitative indicators of safety performance. This work, performed under the Risk-Based Performance Indicator (RBPI) Project, FIN A-3295, for the Office of Research (RES), is considered part of NRC's Performance Indicator Program which is being coordinated through the Office for the Analysis and Evaluation of Operational Data (AEOD). The program originally focused on risk-based indicators at high levels of safety indices (e.g., core-damage frequency, functional unavailabilities, and sequence monitoring). The program was then redirected towards a more amenable goal, safety system unavailability indicators, mainly due to the lack of PRA models and plant data. In that regard, BNL published a technical report that introduced the concept of cycle-based indicators and also described various alternatives of monitoring safety system unavailabilities. Further simplification of these indicators was requested by NRC to facilitate their applications to all plants in a timely manner. This resulted in the development of Safety System Function Trend (SSFT) indicators which minimize the need for detailed system model as well as component history. The theoretical bases for these indicators were developed through various simulation studies to determine the ease of detecting a trend and/or unacceptable performance. These indicators, along with several other indicators, were then generated and compared using plant data as a part of a test application. The SSFT indicators, specifically, were constructed for a total of eight plants, consisting of two systems per plant. Emphasis was placed on examining relative changes, as well as the indicator's actual level. Both the trend and actual indicator level were found to be important in identifying plants with potential problems

  12. Can Leader–Member Exchange Contribute to Safety Performance in An Italian Warehouse?

    Directory of Open Access Journals (Sweden)

    Marco G. Mariani

    2017-05-01

    Full Text Available Introduction: The research considers safety climate in a warehouse and wants to analyze the Leader–Member Exchange (LMX role in respect to safety performance. Griffin and Neal’s safety model was adopted and Leader-Member Exchange was inserted as moderator in the relationships between safety climate and proximal antecedents (motivation and knowledge of safety performance constructs (compliance and participation.Materials and Methods: Survey data were collected from a sample of 133 full-time employees in an Italian warehouse. The statistical framework of Hayes (2013 was adopted for moderated mediation analysis.Results: Proximal antecedents partially mediated the relationship between Safety climate and safety participation, but not safety compliance. Moreover, the results from the moderation analysis showed that the Leader–Member Exchange moderated the influence of safety climate on proximal antecedents and the mediation exist only at the higher level of LMX.Conclusion: The study shows that the different aspects of leadership processes interact in explaining individual proficiency in safety practices.Practical Implications: Organizations as warehouses should improve the quality of the relationship between a leader and a subordinate based upon the dimensions of respect, trust, and obligation for high level of safety performance.

  13. Validation of risk-based performance indicators: Safety system function trends

    International Nuclear Information System (INIS)

    Boccio, J.L.; Vesely, W.E.; Azarm, M.A.; Carbonaro, J.F.; Usher, J.L.; Oden, N.

    1989-10-01

    This report describes and applies a process for validating a model for a risk-based performance indicator. The purpose of the risk-based indicator evaluated, Safety System Function Trend (SSFT), is to monitor the unavailability of selected safety systems. Interim validation of this indicator is based on three aspects: a theoretical basis, an empirical basis relying on statistical correlations, and case studies employing 25 plant years of historical data collected from five plants for a number of safety systems. Results using the SSFT model are encouraging. Application of the model through case studies dealing with the performance of important safety systems shows that statistically significant trends in, and levels of, system performance can be discerned which thereby can provide leading indications of degrading and/or improving performances. Methods for developing system performance tolerance bounds are discussed and applied to aid in the interpretation of the trends in this risk-based indicator. Some additional characteristics of the SSFT indicator, learned through the data-collection efforts and subsequent data analyses performed, are also discussed. The usefulness and practicality of other data sources for validation purposes are explored. Further validation of this indicator is noted. Also, additional research is underway in developing a more detailed estimator of system unavailability. 9 refs., 18 figs., 5 tabs

  14. A road safety performance indicator for vehicle fleet compatibility.

    NARCIS (Netherlands)

    Christoph, M. Vis, M.A. Rackliff, L. & Stipdonk, H.

    2013-01-01

    This paper discusses the development and the application of a safety performance indicator which measures the intrinsic safety of a country's vehicle fleet related to fleet composition. The indicator takes into account both the ‘relative severity’ of individual collisions between different vehicle

  15. Strengthening the culture of safety and performance in nuclear installations

    International Nuclear Information System (INIS)

    Briant, V.S.; Germann, R.P.

    1997-01-01

    In mid-1995, the International Atomic Energy Agency (IAEA) in Vienna brought together a group of safety culture experts from around the world to explore and summarize those practices they viewed as important in establishing sound safety cultures in nuclear installations. This paper will summarize key findings of the Vienna team and also expand those ideas based on related work in which the authors are engaged. The paper includes a definition of safety culture, a description of three stages of safety culture, and five key practices essential to establishing and maintaining a sound safety culture. Additionally, the authors contradicts the conventional view of safety and production as trade-offs, supporting the Vienna team's conclusion that the principles, attitudes, and practices which bring about sustained levels of high performance are the same as those which enhance safety. Based on input from colleagues in several countries, this appears to hold true across geographical and ethnic boundaries. The authors also discuss how this information can be put to practical use to obtain an objective, measurable, and repeated assessment of the current state of the safety culture within a company, plant or work unit. With that information, leaders are then in the position to act on any of the several parameters which affect both safety and performance effectiveness. (author)

  16. Performance Monitoring for Nuclear Safety Related Instrumentation at PUSPATI TRIGA Reactor (RTP)

    International Nuclear Information System (INIS)

    Zareen Khan Abdul Jalil Khan; Ridzuan Abdul Mutalib; Mohd Sabri Minhat

    2015-01-01

    The Reactor TRIGA PUSPATI (RTP) at Malaysia Nuclear Agency is a TRIGA Mark II type reactor and pool type cooled by natural circulation of light water. This paper describe on performance monitoring for nuclear safety related instrumentation in TRIGA PUSPATI Reactor (RTP) of based on various parameter of reactor safety instrument channel such as log power, linear power, Fuel temperature, coolant temperature will take into consideration. Methodology of performance on estimation and monitoring is to evaluate and analysis of reactor parameters which is important of reactor safety and control. And also to estimate power measurement, differential of log and linear power and fuel temperature during reactor start-up, operation and shutdown .This study also focus on neutron power fluctuation from fission chamber during reactor start-up and operation. This work will present result of performance monitoring from RTP which indicated the safety parameter identification and initiate safety action on crossing the threshold set point trip. Conclude that performance of nuclear safety related instrumentation will improved the reactor control and safety parameter during reactor start-up, operation and shutdown. (author)

  17. Transformational leadership and employee safety performance: a within-person, between-jobs design.

    Science.gov (United States)

    Inness, Michelle; Turner, Nick; Barling, Julian; Stride, Chris B

    2010-07-01

    We investigated the extent to which the safety performance (i.e., self-reported safety compliance and safety participation) of employees with 2 jobs was predicted by their respective supervisors' transformational leadership behaviors. We compared 2 within-person models: a context-specific model (i.e., transformational leadership experienced by employees in 1 context related to those same employees' safety performance only in that context) and a context-spillover model (i.e., transformational leadership experienced by employees in 1 context related to those same employees' safety performance in the same and other contexts). Our sample comprised 159 "moonlighters" (73 men, 86 women): employees who simultaneously hold 2 different jobs, each with a different supervisor, providing within-person data on the influence of different supervisors on employee safety performance across 2 job contexts. Having controlled for individual differences (negative affectivity and conscientiousness) and work characteristics (e.g., hours worked and length of relationship with supervisor), the context-specific model provided the best fit to the data among alternative nested models. Implications for the role of transformational leadership in promoting workplace safety are discussed.

  18. Risk-based performance indicators

    International Nuclear Information System (INIS)

    Azarm, M.A.; Boccio, J.L.; Vesely, W.E.; Lofgren, E.

    1987-01-01

    The purpose of risk-based indicators is to monitor plant safety. Safety is measured by monitoring the potential for core melt (core-melt frequency) and the public risk. Targets for these measures can be set consistent with NRC safety goals. In this process, the performance of safety systems, support systems, major components, and initiating events can be monitored using measures such as unavailability, failure or occurrence frequency. The changes in performance measures and their trends are determined from the time behavior of monitored measures by differentiation between stochastical and actual variations. Therefore, degradation, as well as improvement in the plant safety performance, can be determined. The development of risk-based performance indicators will also provide the means to trace a change in the safety measures to specific problem areas which are amenable to root cause analysis and inspection audits. In addition, systematic methods will be developed to identify specific improvement policies using the plant information system for the identified problem areas. The final product of the performance indicator project will be a methodology, and an integrated and validated set of software packages which, if properly interfaced with the logic model software of a plant, can monitor the plant performance as plant information is provided as input

  19. Engineering Solutions to Enhance Traffic Safety Performance on Two-Lane Highways

    Directory of Open Access Journals (Sweden)

    Lina Wu

    2015-01-01

    Full Text Available Improving two-lane highway traffic safety conditions is of practical importance to the traffic system, which has attracted significant research attention within the last decade. Many cost-effective and proactive solutions such as low-cost treatments and roadway safety monitoring programs have been developed to enhance traffic safety performance under prevailing conditions. This study presents research perspectives achieved from the Highway Safety Enhancement Project (HSEP that assessed safety performance on two-lane highways in Beijing, China. Potential causal factors are identified based on proposed evaluation criteria, and primary countermeasures are developed against inferior driving conditions such as sharp curves, heavy gradients, continuous downgrades, poor sight distance, and poor clear zones. Six cost-effective engineering solutions were specifically implemented to improve two-lane highway safety conditions, including (1 traffic sign replacement, (2 repainting pavement markings, (3 roadside barrier installation, (4 intersection channelization, (5 drainage optimization, and (6 sight distance improvement. The effectiveness of these solutions was examined and evaluated based on Empirical Bayes (EB models. The results indicate that the proposed engineering solutions effectively improved traffic safety performance by significantly reducing crash occurrence risks and crash severities.

  20. Impact of individual resilience and safety climate on safety performance and psychological stress of construction workers: A case study of the Ontario construction industry.

    Science.gov (United States)

    Chen, Yuting; McCabe, Brenda; Hyatt, Douglas

    2017-06-01

    The construction industry has hit a plateau in terms of safety performance. Safety climate is regarded as a leading indicator of safety performance; however, relatively little safety climate research has been done in the Canadian construction industry. Safety climate may be geographically sensitive, thus it is necessary to examine how the construct of safety climate is defined and used to improve safety performance in different regions. On the other hand, more and more attention has been paid to job related stress in the construction industry. Previous research proposed that individual resilience may be associated with a better safety performance and may help employees manage stress. Unfortunately, few empirical research studies have examined this hypothesis. This paper aims to examine the role of safety climate and individual resilience in safety performance and job stress in the Canadian construction industry. The research was based on 837 surveys collected in Ontario between June 2015 and June 2016. Structural equation modeling (SEM) techniques were used to explore the impact of individual resilience and safety climate on physical safety outcomes and on psychological stress among construction workers. The results show that safety climate not only affected construction workers' safety performance but also indirectly affected their psychological stress. In addition, it was found that individual resilience had a direct negative impact on psychological stress but had no impact on physical safety outcomes. These findings highlight the roles of both organizational and individual factors in individual safety performance and in psychological well-being. Construction organizations need to not only monitor employees' safety performance, but also to assess their employees' psychological well-being. Promoting a positive safety climate together with developing training programs focusing on improving employees' psychological health - especially post-trauma psychological

  1. Transient performance analysis of pressurized safety injection tank with a partition

    International Nuclear Information System (INIS)

    Bae, Youngmin; Kim, Young In; Kim, Keung Koo

    2015-01-01

    Highlights: • Functional performance of safety injection tanks with a partition is evaluated. • Effects of key design parameters are scrutinized. • Distinctive features of the flow in multi-unit safety injection tanks are explored. - Abstract: A parametric study has been performed to evaluate the functional performance of a pressurized multi-unit safety injection tank, which would be considered as one of the candidates for a passive safety injection system in a nuclear power plant. The influences of key design parameters including the orifice size, initial gas fraction, and resistance coefficients and operating condition on the injection flow rate are scrutinized with a discussion of the relevant flow features such as the choked flow of gas through an orifice and two interconnected regions of differing gaseous pressure. The obtained results indicate that a multi-unit safety injection tank can passively control the injection flow rate and provide a stable safety injection over a relatively long period even in the case of drastic depressurization of a reactor coolant system

  2. SGHWR fuel performance, safety and reliability

    International Nuclear Information System (INIS)

    Pickman, D.O.; Inglis, G.H.

    1977-05-01

    The design principles involved in fuel pins and elements need to take account of the sometimes conflicting requirements of safety and reliability. The principal factors involved in this optimisation are discussed and it is shown from fuel irradiation experience in the Winfrith SGHWR that the necessary bias towards safety has not resulted in a reliability level lower than that shown by other successful water reactor designs. Reliability has important economic implications. By a detailed evaluation of SGHWR fuel defects it is shown that very few defects can be shown to be related to design, rating, or burn-up. This demonstrates that economic aspects have not over-ridden necessary criteria that most be met to achieve the desirable reliability level. It is possible that large scale experience on SGHWR fuel may eventually demonstrate that the balance is too much in favour of reliability and consideration may be given to whether design changes favouring economy could be achieved without compromising safety. The safety criteria applied to SGHWR fuel are designed to avoid any possibility of a temperature runaway in any credible accident situation. the philosophy and supporting experimental work programme are outlines and the fuel design features which particularly contribute to maximising safety margins are outlined. Reference is made to the new 60-pin fuel element to be used in the commercial SGHWRs and to its comparison in design and performance aspects with the 36-pin element that has been used to date in the Winfrith SGHWR. (author)

  3. Experience with performance based training of nuclear criticality safety engineers

    International Nuclear Information System (INIS)

    Taylor, R.G.

    1993-01-01

    For non-reactor nuclear facilities, the U.S. Department of Energy (DOE) does not require that nuclear criticality safety engineers demonstrate qualification for their job. It is likely, however, that more formalism will be required in the future. Current DOE requirements for those positions which do have to demonstrate qualification indicate that qualification should be achieved by using a systematic approach such as performance based training (PBT). Assuming that PBT would be an acceptable mechanism for nuclear criticality safety engineer training in a more formal environment, a site-specific analysis of the nuclear criticality safety engineer job was performed. Based on this analysis, classes are being developed and delivered to a target audience of newer nuclear criticality safety engineers. Because current interest is in developing training for selected aspects of the nuclear criticality safety engineer job, the analysis is incompletely developed in some areas

  4. Building quality into performance and safety assessment software

    International Nuclear Information System (INIS)

    Wojciechowski, L.C.

    2011-01-01

    Quality assurance is integrated throughout the development lifecycle for performance and safety assessment software. The software used in the performance and safety assessment of a Canadian deep geological repository (DGR) follows the CSA quality assurance standard CSA-N286.7 [1], Quality Assurance of Analytical, Scientific and Design Computer Programs for Nuclear Power Plants. Quality assurance activities in this standard include tasks such as verification and inspection; however, much more is involved in producing a quality software computer program. The types of errors found with different verification methods are described. The integrated quality process ensures that defects are found and corrected as early as possible. (author)

  5. Strengthening the culture of safety and performance in nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    Briant, V S [GPU Nuclear, Parsippany (United States); Germann, R P [Aberdeen Center for Team Learning, Matawan (United States)

    1997-07-01

    In mid-1995, the International Atomic Energy Agency (IAEA) in Vienna brought together a group of safety culture experts from around the world to explore and summarize those practices they viewed as important in establishing sound safety cultures in nuclear installations. This paper will summarize key findings of the Vienna team and also expand those ideas based on related work in which the authors are engaged. The paper includes a definition of safety culture, a description of three stages of safety culture, and five key practices essential to establishing and maintaining a sound safety culture. Additionally, the authors contradicts the conventional view of safety and production as trade-offs, supporting the Vienna team`s conclusion that the principles, attitudes, and practices which bring about sustained levels of high performance are the same as those which enhance safety. Based on input from colleagues in several countries, this appears to hold true across geographical and ethnic boundaries. The authors also discuss how this information can be put to practical use to obtain an objective, measurable, and repeated assessment of the current state of the safety culture within a company, plant or work unit. With that information, leaders are then in the position to act on any of the several parameters which affect both safety and performance effectiveness. (author) 9 refs., 5 tabs.

  6. Incorporating Workplace Injury to Measure the Safety Performance of Industrial Sectors in Taiwan

    Directory of Open Access Journals (Sweden)

    Li-Ting Yeh

    2017-12-01

    Full Text Available The severity of workplace injuries varies by industry. Information on workplace injuries can enable firms and governments to effectively improve their safety performance based on the specific contexts of each industry. Incorporating the three workplace injury rates (being wounded or ill, disability, and death, a data envelopment analysis (DEA model is developed to evaluate the safety performance of 17 industrial sectors in Taiwan. The results suggest that the Taiwanese government should pay particular attention to the mining and quarrying industry, which has the lowest safety performance. Additionally, the results provide abundant information for the Taiwanese government to design industry safety regulations in a way that may prompt firms to develop a sustainable economy by improving their health and safety practices and enhancing their overall safety performance.

  7. The safety culture change process performed in Polish research reactor MARIA

    International Nuclear Information System (INIS)

    Golab, Andrzej

    2002-01-01

    The Safety Culture Change Process Performed in research reactor MARIA is described in this paper. The essential issues fulfilled in realization of the Safety Culture Enhancement Programme are related to the attitude and behaviour of top management, co-operating groups, operational personnel, relations between the operating organization and the supervising and advising organizations. Realization of this programme is based on changing the employees understanding of safety, changing their attitudes and behaviours by means of adequate training, requalification process and performing the broad self-assessment programme. Also a high level Quality Assurance Programme helps in development of the Safety Culture. (author)

  8. Development of Safety Grade PLC (POSAFE-Q) and Performance Test Results

    International Nuclear Information System (INIS)

    Kim, Chang Hwoi; Park, Won Man; Choi, Jong Gyun; Lee, Dong Young; No, Young Hun; Song, Seung Hwan

    2006-01-01

    The safety grade PLC (POSAFE-Q) is being developed in the Korea Nuclear Instrumentation and Control System (KNICS) R and D project. The PLC satisfies Safety Class 1E, Quality Class 1, and Seismic Category I. The software such as the RTOS and firmware are being developed according to the safety critical software life cycle. Especially, the formal method is applied to design the SRS (Software Requirement Spec.) and the SDS (Software Design Specification.) to be error-free. The POSAFE-Q has several modules such as processor module, input and output modules, communication modules, redundant processor module, redundant power modules, etc,. To verify the function and performance, several tests such as CT, IT and ST were performed. And also, the equipment qualification test for environment, EMI and EMC, and seismic ware performed. All tests are satisfied with the requirements and specification for safety grade PLC, and the criteria for safety system in nuclear power plants

  9. Development of Safety Grade PLC (POSAFE-Q) and Performance Test Results

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Chang Hwoi; Park, Won Man; Choi, Jong Gyun; Lee, Dong Young [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); No, Young Hun; Song, Seung Hwan [POSCON, Seoul (Korea, Republic of)

    2006-07-01

    The safety grade PLC (POSAFE-Q) is being developed in the Korea Nuclear Instrumentation and Control System (KNICS) R and D project. The PLC satisfies Safety Class 1E, Quality Class 1, and Seismic Category I. The software such as the RTOS and firmware are being developed according to the safety critical software life cycle. Especially, the formal method is applied to design the SRS (Software Requirement Spec.) and the SDS (Software Design Specification.) to be error-free. The POSAFE-Q has several modules such as processor module, input and output modules, communication modules, redundant processor module, redundant power modules, etc,. To verify the function and performance, several tests such as CT, IT and ST were performed. And also, the equipment qualification test for environment, EMI and EMC, and seismic ware performed. All tests are satisfied with the requirements and specification for safety grade PLC, and the criteria for safety system in nuclear power plants.

  10. Physician job satisfaction related to actual and preferred job size

    NARCIS (Netherlands)

    Schmit Jongbloed, Lodewijk J.; Cohen-Schotanus, Janke; Borleffs, Jan C. C.; Stewart, Roy E.; Schonrock-Adema, Johanna

    2017-01-01

    Background: Job satisfaction is essential for physicians' well-being and patient care. The work ethic of long days and hard work that has been advocated for decades is acknowledged as a threat for physicians' job satisfaction, well-being, and patient safety. Our aim was to determine the actual and

  11. Performance and safety of hydraulic turbines

    International Nuclear Information System (INIS)

    Brekke, H

    2010-01-01

    The first part of the paper contains the choice of small turbines for run of the river power plants. Then a discussion is given on the optimization of the performance of different types of large turbines. Finally a discussion on the safety and necessary maintenance of turbines is given with special attention to bolt connections.

  12. Applying importance-performance analysis to patient safety culture.

    Science.gov (United States)

    Lee, Yii-Ching; Wu, Hsin-Hung; Hsieh, Wan-Lin; Weng, Shao-Jen; Hsieh, Liang-Po; Huang, Chih-Hsuan

    2015-01-01

    The Sexton et al.'s (2006) safety attitudes questionnaire (SAQ) has been widely used to assess staff's attitudes towards patient safety in healthcare organizations. However, to date there have been few studies that discuss the perceptions of patient safety both from hospital staff and upper management. The purpose of this paper is to improve and to develop better strategies regarding patient safety in healthcare organizations. The Chinese version of SAQ based on the Taiwan Joint Commission on Hospital Accreditation is used to evaluate the perceptions of hospital staff. The current study then lies in applying importance-performance analysis technique to identify the major strengths and weaknesses of the safety culture. The results show that teamwork climate, safety climate, job satisfaction, stress recognition and working conditions are major strengths and should be maintained in order to provide a better patient safety culture. On the contrary, perceptions of management and hospital handoffs and transitions are important weaknesses and should be improved immediately. Research limitations/implications - The research is restricted in generalizability. The assessment of hospital staff in patient safety culture is physicians and registered nurses. It would be interesting to further evaluate other staff's (e.g. technicians, pharmacists and others) opinions regarding patient safety culture in the hospital. Few studies have clearly evaluated the perceptions of healthcare organization management regarding patient safety culture. Healthcare managers enable to take more effective actions to improve the level of patient safety by investigating key characteristics (either strengths or weaknesses) that healthcare organizations should focus on.

  13. The role of performance assessment in validation, regulation and public acceptance

    International Nuclear Information System (INIS)

    Pigford, T.H.

    1992-01-01

    This paper reports that regulation of public health and safety for a geologic repository for radioactive waste requires that performance assessment show that radioactive releases will not violate a safety limit. Accurate predictions of actual performance are not required. Because of the long times in the future when radioactivity can be released, performance predictions must be based on sound hypothesis of the mechanisms that control and mitigate releases. Such hypotheses are useful only if they lead to clear mathematical formulations, specify clearly the parameters that are expected to control the releases, and specify means of accelerated testing or other means for validating the hypotheses. useful hypotheses usually lead to conservative and bounding analyses that can be more reliable for this purpose than efforts to predict actual repository performance

  14. Safety performance evaluation of converging chevron pavement markings : final report.

    Science.gov (United States)

    2014-12-01

    The objectives of this study were (1) to perform a detailed safety analysis of converging chevron : pavement markings, quantifying the potential safety benefits and developing an understanding of the : incident types addressed by the treatment, and (...

  15. Safety Performance Index Industri Batik Tulis Berdasarkan Kriteria Majemuk

    Directory of Open Access Journals (Sweden)

    Nachnul Ansori

    2015-12-01

    Full Text Available Accident generally occurs due to the activities which is done in unsafe conditions or even unsafe behavior. These conditions can influence workers productivity. In batik industries, those workers use toxic material and work in non ergonomic atmosphere. Moreover, they also do not take care of the environment and do not use personal protective equipments (PPE. Workers at Madura batik SMEs have not fully realized the significance of occupational health and safety (OHS in their working areas. The aims of this research is to evaluate OHS performance based on the indicators of safety performance index (SPI, which is multicriteria, in that industri. The safety performance attributes were obtained from factor analysis from the previous study. The index is calculated based on the weighted evaluation results of critical behavior checklist (CBC, integrated with analytical hierarchy process (AHP. As the results, we should give priority to improve the knowledge and experience toward OHS of the workers and also improve the working environment of the Madura’s batik industries. Additionally, the performance of OHS in coloring process is also on the threshold of unsafe condition, further development on the coloring process is needed.

  16. Experience of safety and performance improvement for fuel handling equipment

    International Nuclear Information System (INIS)

    Gyoon Chang, Sang; Hee Lee, Dae

    2014-01-01

    The purpose of this study is to provide experience of safety and performance improvement of fuel handling equipment for nuclear power plants in Korea. The fuel handling equipment, which is used as an important part of critical processes during the refueling outage, has been improved to enhance safety and to optimize fuel handling procedures. Results of data measured during the fuel reloading are incorporated into design changes. The safety and performance improvement for fuel handling equipment could be achieved by simply modifying the components and improving the interlock system. The experience provided in this study can be useful lessons for further improvement of the fuel handling equipment. (authors)

  17. Analysis on Occupants’ Satisfaction for Safety Performance Assessment in Low Cost Housing

    Directory of Open Access Journals (Sweden)

    Husin Husrul Nizam

    2014-01-01

    Full Text Available The delivery performance of the low cost housing is questioned since the occupants are prone towards safety hazards in the housing complex, such as structural instability and falling building fragments. Without defining the occupants’ requirements for the development of low cost housing, the prevailing safety factors are hard to be determined. This paper explores the rationale of safety performance assessment in the low cost housing by considering the occupants’ participation to achieve a better safety provision during occupancy period. Questionnaire survey was distributed to 380 occupants of the low cost housing in Kuala Lumpur and Selangor, Malaysia. The result shows that 80.8% of the respondents had expressed their dissatisfaction with the safety performance of the lift. By referring to the mode of ranking level, the most significant aspect rated by the respondents is Building Safety Features, with 51.6% respondents. The attained aspects can be fundamental parameters which can be considered in the future development of low cost housing.

  18. Experience with performance based training of nuclear criticality safety engineers

    International Nuclear Information System (INIS)

    Taylor, R.G.

    1993-01-01

    Historically, new entrants to the practice of nuclear criticality safety have learned their job primarily by on-the-job training (OJT) often by association with an experienced nuclear criticality safety engineer who probably also learned their job by OJT. Typically, the new entrant learned what he/she needed to know to solve a particular problem and accumulated experience as more problems were solved. It is likely that more formalism will be required in the future. Current US Department of Energy requirements for those positions which have to demonstrate qualification indicate that it should be achieved by using a systematic approach such as performance based training (PBT). Assuming that PBT would be an acceptable mechanism for nuclear criticality safety engineer training in a more formal environment, a site-specific analysis of the nuclear criticality safety engineer job was performed. Based on this analysis, classes are being developed and delivered to a target audience of newer nuclear criticality safety engineers. Because current interest is in developing training for selected aspects of the nuclear criticality safety engineer job, the analysis i's incompletely developed in some areas. Details of this analysis are provided in this report

  19. Research on the actual condition on the licensed chief engineers of radiation

    International Nuclear Information System (INIS)

    1976-01-01

    A research on the actual condition on the licensed chief engineers of radiation was performed on October, 1975. Question cards were sent to 2915 facilities in Japan, and answers came back from 2850 facilities. Answers report the size of each facility, number of employee, number of chief engineers in charge, age of chief engineers, appointment authority, responsibility, improvement of working condition of chief engineer, and assistant officer for chief engineer. The number of worker is 62,456 in 2,769 facilities. The number of chief engineer in charge is 3,286 containing 579 doctor and/or dentist. The age of chief in 80 percent facilities is above 31. System of management of radiation safety was also investigated. (Kato, T.)

  20. A comparative study of three types of grid connected photovoltaic systems based on actual performance

    International Nuclear Information System (INIS)

    Ya’acob, M. Effendy; Hizam, Hashim; Khatib, Tamer; Radzi, M. Amran M.

    2014-01-01

    Highlights: • We present and analyze actual performance of three types of PV systems in the tropics. • We present conclusion and recommendations for sun tracking systems and CPV. • We present worthwhile experiment results for those who are interested in PV system. - Abstract: In this study, three photovoltaic (PV) systems are evaluated based on actual performance. The energy generation of three types of PV systems namely concentrating PV system (6 units × 1 kWp), PV system with sun tracking flat (2 units × 1 kWp) and fixed flat PV system (2 units × 1 kWp) is analyzed in this research. Data analysis for ten consecutive months consisting of 12,190 samples of 15 min interval is done. The performance evaluation is done using energy yield, yield factor, capacity factor, power efficiency and PV array efficiency. Based on the experiment data, it is concluded that tracking flat PV system is the most suitable system for Malaysia in normal operation mode with average daily generation of 4.7 kW h (141 kW h as a monthly average), system efficiency of 11%, power efficiency of 85%, average daily yield factor of 2.3 kW h/kWp and capacity factor of 32%. This study also highlights the PV energy (E PV ) models for each PV generators with respect to the environmental factors. The advantage of employing a tracking flat system as compared to the fixed flat system is considered based on the effectiveness of the dual-axis tracking mechanism tracking the sun for maximum power output

  1. Investigation on regulatory requirements for radiation safety management

    International Nuclear Information System (INIS)

    Han, Eun Ok; Choi, Yoon Seok; Cho, Dae Hyung

    2013-01-01

    NRC recognizes that efficient management of radiation safety plan is an important factor to achieve radiation safety service. In case of Korea, the contents to perform the actual radiation safety management are legally contained in radiation safety management reports based on the Nuclear Safety Act. It is to prioritize the importance of safety regulations in each sector in accordance with the current situation of radiation and radioactive isotopes-used industry and to provide a basis for deriving safety requirements and safety regulations system maintenance by the priority of radiation safety management regulations. It would be helpful to achieve regulations to conform to reality based on international standards if consistent safety requirements is developed for domestic users, national standards and international standards on the basis of the results of questions answered by radiation safety managers, who lead on-site radiation safety management, about the priority of important factors in radioactive sources use, sales, production, moving user companies, to check whether derived configuration requirements for radiation safety management are suitable for domestic status

  2. The European atomic politics under the treaty of Lisboa and actual questions of the export of nuclear waste

    International Nuclear Information System (INIS)

    Ehlenz, Christian; Frenz, Walter

    2011-01-01

    In the context of the actual discussion considerably influenced by safety questions activated by the reactor accident in Tschernobyl in 1986, the EAG gains increasing significance. However, a substantial safety risk proceeds not only with nuclear power stations as a possible goal for attacks of terror, but also from the uncontrolled spreading with nuclear material. The latter equally affects the question on handling radioactive waste materials being straightly discussed in Germany as well as in the European Union as proven by the European Union commissioner Oettinger. This is to be considered in connection with the problem how extensively the competences of the Euratom for the nuclear safety may be interpreted. The actual changes of the legal situation by means of the Lisboa contract for the EAG altogether turned out marginally and let its demand for a reform based on the actual conditions appear more urgent.

  3. 29 CFR 1960.11 - Evaluation of occupational safety and health performance.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 9 2010-07-01 2010-07-01 false Evaluation of occupational safety and health performance. 1960.11 Section 1960.11 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH... AND HEALTH PROGRAMS AND RELATED MATTERS Administration § 1960.11 Evaluation of occupational safety and...

  4. Comparing performance level estimation of safety functions in three distributed structures

    International Nuclear Information System (INIS)

    Hietikko, Marita; Malm, Timo; Saha, Heikki

    2015-01-01

    The capability of a machine control system to perform a safety function is expressed using performance levels (PL). This paper presents the results of a study where PL estimation was carried out for a safety function implemented using three different distributed control system structures. Challenges relating to the process of estimating PLs for safety related distributed machine control functions are highlighted. One of these examines the use of different cabling schemes in the implementation of a safety function and its effect on the PL evaluation. The safety function used as a generic example in PL calculations relates to a mobile work machine. It is a safety stop function where different technologies (electrical, hydraulic and pneumatic) can be utilized. It was detected that by replacing analogue cables with digital communication the system structure becomes simpler with less number of failing components, which can better the PL of the safety function. - Highlights: • Integration in distributed systems enables systems with less components. • It offers high reliability and diagnostic properties. • Analogue signals create uncertainty in signal reliability and difficult diagnostics

  5. Performance indicators and combining assessments to evaluate the safety performance of licensees

    International Nuclear Information System (INIS)

    Aubrey, Richard; Van Binnebeek, J.J.; Warren, T.F.H.

    1998-01-01

    The CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries. As a follow-up to the 1995 document on Compilation of Responses to a Questionnaire on the Evaluation of the Safety Performance of Licensees, WGIP members identified several issues where additional information would be useful in future meetings and discussions. The consensus of the Group was that performance indicators (PIs) and how assessments are combined were the two issues that should be addressed first. It was noted also that in addition to information in obtained through the questionnaire, results from the workshop in May 1996 may provide valuable input to the endeavour. This report summarises a review conducted of the PI-related information provided by the questionnaire, the workshop, and responses from WGIP members to a request for specific information not addressed previously

  6. Evaluation of operating experience for early recognition of deteriorating safety performance

    International Nuclear Information System (INIS)

    Beckmerhagen, I.A.; Berg, H.P.

    2004-01-01

    One of the most difficult challenges facing nuclear power plants is to recognize the early signs of degrading safety performance before regulatory requirements are imposed or serious incidents or accidents occur. Today, the nuclear industry is striving for collecting more information on occurrences that could improve the operational safety performance. To achieve this, the reporting threshold has been lowered from incidents to anomalies with minor or no impact to safety. Industry experience (also outside nuclear industry) has shown that these are typical issues which should be considered when looking for such early warning signs. Therefore, it is important that nuclear power plant operators have the capability to trend, analyse and recognize early warning signs of deteriorating performance. It is necessary that plant operators are sensitive to these warning signs which may not be immediately evident. Reviewing operating experience is one of the main tasks for plant operators in their daily activities. Therefore, self assessment should be at the centre of any operational safety performance programme. One way of applying a self assessment program is through the following four basic elements: operational data, events, safety basis, and related experience. This approach will be described in the paper in more details. (authors)

  7. Validation testing of safety-critical software

    International Nuclear Information System (INIS)

    Kim, Hang Bae; Han, Jae Bok

    1995-01-01

    A software engineering process has been developed for the design of safety critical software for Wolsung 2/3/4 project to satisfy the requirements of the regulatory body. Among the process, this paper described the detail process of validation testing performed to ensure that the software with its hardware, developed by the design group, satisfies the requirements of the functional specification prepared by the independent functional group. To perform the tests, test facility and test software were developed and actual safety system computer was connected. Three kinds of test cases, i.e., functional test, performance test and self-check test, were programmed and run to verify each functional specifications. Test failures were feedback to the design group to revise the software and test results were analyzed and documented in the report to submit to the regulatory body. The test methodology and procedure were very efficient and satisfactory to perform the systematic and automatic test. The test results were also acceptable and successful to verify the software acts as specified in the program functional specification. This methodology can be applied to the validation of other safety-critical software. 2 figs., 2 tabs., 14 refs. (Author)

  8. Investigation of thermolytic hydrogen generation rate of tank farm simulated and actual waste

    Energy Technology Data Exchange (ETDEWEB)

    Martino, C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Newell, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Woodham, W. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Pareizs, J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Edwards, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Howe, A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-11-15

    To support resolution of Potential Inadequacies in the Safety Analysis for the Savannah River Site (SRS) Tank Farm, Savannah River National Laboratory conducted research to determine the thermolytic hydrogen generation rate (HGR) with simulated and actual waste. Gas chromatography methods were developed and used with air-purged flow systems to quantify hydrogen generation from heated simulated and actual waste at rates applicable to the Tank Farm Documented Safety Analysis (DSA). Initial simulant tests with a simple salt solution plus sodium glycolate demonstrated the behavior of the test apparatus by replicating known HGR kinetics. Additional simulant tests with the simple salt solution excluding organics apart from contaminants provided measurement of the detection and quantification limits for the apparatus with respect to hydrogen generation. Testing included a measurement of HGR on actual SRS tank waste from Tank 38. A final series of measurements examined HGR for a simulant with the most common SRS Tank Farm organics at temperatures up to 140 °C. The following conclusions result from this testing.

  9. INPO Perspectives and Activities to Enhance Supplier Human Performance and Safety Culture

    International Nuclear Information System (INIS)

    Duncan, R. J.

    2016-01-01

    Within their own organizations, utilities have made significant improvements in human performance and safety culture, supported by a strong community of practice through INPO and WANO. In recent years, utilities have been making increasing use of suppliers for design, construction, inspection and maintenance services in support of their NPPs. Many of these suppliers do not have the benefit of being members of a community of practice when it comes to human performance and safety culture. To help the supplier community make improvements similar to what the utilities have achieved, INPO has recently expanded its Supplier Participant program to address the issue of human performance and safety culture in the supplier community. The intent of this paper will be to share the INPO’s perspectives and activities in helping suppliers of services and products to NPPs enhance their human performance and safety culture. (author)

  10. Containment-emergency-sump performance. Technical findings related to Unresolved Safety Issue A-43

    International Nuclear Information System (INIS)

    1983-04-01

    This report summarizes key technical findings related to the Unresolved Safety Issue A-43, Containment Emergency Sump Performance, and provides recommendations for resolution of attendant safety issues. The key safety questions relate to: (a) effects of insulation debris on sump performance; (b) sump hydraulic performance as determined by design features, submergence, and plant induced effects, and (c) recirculation pump performance wherein air and/or particulate ingestion can occur. The technical findings presented in this report provide information relevant to the design and performance evaluation of the containment emergency sump

  11. Actual performance of mechanical ventilators in ICU: a multicentric quality control study

    Directory of Open Access Journals (Sweden)

    Govoni L

    2012-12-01

    Full Text Available Leonardo Govoni,1 Raffaele L Dellaca,1 Oscar Peñuelas,2,3 Giacomo Bellani,4,5 Antonio Artigas,3,6 Miquel Ferrer,3,7 Daniel Navajas,3,8,9 Antonio Pedotti,1 Ramon Farré3,81TBM-Lab, Dipartimento di Bioingegneria, Politecnico di Milano University, Milano, Italy; 2Hospital Universitario de Getafe – CIBERES, Madrid, Spain; 3CIBER de Enfermedades Respiratorias, Bunyola, Spain; 4Department of Experimental Medicine, University of Milan, Bicocca, Italy; 5Department of Perioperative Medicine and Intensive Care, San Gerardo Hospital, Monza (MI, Italy; 6Critical Care Center, Sabadell Hospital, Corporació Sanitaria Universitaria Parc Tauli, Universitat Autonoma de Barcelona, CIBERES, Spain; 7Department of Pneumology, Hospital Clinic, IDIBAPS, Barcelona, Spain; 8Unitat de Biofísica i Bioenginyeria, Facultat de Medicina, Universidad de Barcelona-IDIBAPS, Barcelona, Spain; 9Institut de Bioenginyeria de Catalunya, Barcelona, SpainAbstract: Even if the performance of a given ventilator has been evaluated in the laboratory under very well controlled conditions, inappropriate maintenance and lack of long-term stability and accuracy of the ventilator sensors may lead to ventilation errors in actual clinical practice. The aim of this study was to evaluate the actual performances of ventilators during clinical routines. A resistance (7.69 cmH2O/L/s – elastance (100 mL/cmH2O test lung equipped with pressure, flow, and oxygen concentration sensors was connected to the Y-piece of all the mechanical ventilators available for patients in four intensive care units (ICUs; n = 66. Ventilators were set to volume-controlled ventilation with tidal volume = 600 mL, respiratory rate = 20 breaths/minute, positive end-expiratory pressure (PEEP = 8 cmH2O, and oxygen fraction = 0.5. The signals from the sensors were recorded to compute the ventilation parameters. The average ± standard deviation and range (min–max of the ventilatory parameters were the following: inspired

  12. Safety Analysis for Enlargement of Allowance Band of Main Steam Safety Valve Opening Setpoint of Wolsong Unit 1

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sungmin [Korea Hydro and Nuclear Power Co., Ltd., Daejeon (Korea, Republic of); Kim, Jonghyun; Cho, Cheonhwey [Atomic Creative Technology Co., Ltd., Daejeon (Korea, Republic of)

    2013-05-15

    The target events were selected to be the two most secondary system pressurization events - Loss of Class IV Power (LOCL4) and Loss of Condenser Vacuum (LOCV). In the actual analysis, an uncertainty of 1% was added to be conservative, so an allowance band of ±4% was used. A safety analysis was performed with CATHENA code to evaluate the safety of increasing the opening setpoint allowance band of MSSVs in WSNPP-1 The analysis results for both LOCL4 and LOCV confirm that the enlarged allowance would bring no harm to the safety of the plant from the viewpoint of fuel integrity and pressure boundary integrity. Therefore, the new allowance band of MSSVs will be incorporated into the Technical Specifications of WSNPP-1.

  13. Safety and protection for large scale superconducting magnets. FY 1984 report

    International Nuclear Information System (INIS)

    Thome, R.J.; Pillsbury, R.D. Jr.; Minervini, J.V.

    1984-11-01

    The Fusion Program is moving rapidly into design and construction of systems using magnets with stored energies in the range of hundreds of megajoules to gigajoules. For example, the toroidal field coil system alone for TFCX would store about 4 GJ and the mirror system MFTF-B would store about 1.6 GJ. Safety and protection analyses of the magnet subsystems become progressively more important as the size and complexity of the installations increase. MIT has been carrying out a program for INEL oriented toward safety and protection in large scale superconducting magnet systems. The program involves collection and analysis of information on actual magnet failures, analyses of general problems associated with safety and protection, and performance of safety oriented experiments. This report summarizes work performed in FY 1984

  14. Potential safety features and safety analysis aspects for high performance light water reactor (HPLWR)

    International Nuclear Information System (INIS)

    Aksan, N.; Schulenberg, T.; Squarer, D.

    2003-01-01

    Research Activities are ongoing worldwide to develop advanced nuclear power plants with high thermal efficiency for the purpose to improve their economical competitiveness. Within the 5th Framework Programme of the European Commission, a project has been launched with the main objective to assess the technical and economical feasibility of a high efficiency LWR operating at super critical pressure conditions. Several European research institutions, industrial partners and the University of Tokyo participated and worked in this common research project. Within the aims of the development of the HPLWR is to use both passive and active safety systems for performing safety related functions in the event of transients or accidents. Consequently substantial effort has been invested in order to define the safety features of the plant in a European environment, as well as to incorporate passive safety features into the design. Throughout this process, the European Utility Requirements (EUR) and requirements known from Generation IV initiative were considered as a guideline in general terms in order to include further advanced ideas. The HPLWR general features were compared to both requirements, indicating a potential to meet these. Since, the supercritical HPLWR represents a challenge for best-estimate safety codes like RELAP5, CATHARE and TRAB due to the fact that these codes were developed for two-phase or single-phase coolant at pressures far below critical point, work on the preliminary assessment of the appropriateness of these codes have been performed for selected relevant phenomena, and application of the codes to the selected transients on the basis of defined 'reference design'. An overview on their successful upgrade to supercritical pressures and application to some plant safety analysis are provided in the paper. Further elaborations in relation to future needs are also discussed. (author)

  15. Work support, psychological well-being and safety performance among nurses in Hong Kong.

    Science.gov (United States)

    Wong, Kenchi C K

    2018-02-06

    This study investigated the mediating role of psychological well-being between work support and safety performance of 314 Hong Kong nurses, using self-reported questionnaires. Results showed that psychological well-being mediated the effects of work support on safety performance. The findings illustrate that work support was an important element to improve psychological well-being. This could generate better safety performance of the nurses. Implications and limitations are discussed.

  16. New safety performance indicators for safety assessment of radioactive waste disposal facilities. Cuban experience

    International Nuclear Information System (INIS)

    Peralta Vital, J.L.; Castillo, R.G.; Olivera, J.

    2002-01-01

    The paper shows the Cuban experience on implementing geological disposal of radioactive waste and the necessity for identifying new safety performance indicators for the safety assessment (SA) of radioactive waste disposal facilities. The selected indicator was the concentration of natural radioactive elements (U, Ra, Th, K) in the Cuban geologic environment. We have carried out a group of investigations, which have allowed characterising the concentration for the whole Country, creating a wide database where this indicator is associated with the lithology. The main lithologies in Cuba are: the sedimentary rocks (70 percent of national occurrence), which are present in the three regions (limestone and lutite), and finally the igneous and metamorphic rocks. The results show the concentrations ranges of the natural radionuclides associated fundamentally to the variation in the lithology and geographical area of the Country. In Cuba, the higher concentration (ppm) of Uranium and Radium are referenced to the Central region associated to Skarn, while for Thorium (ppm) and Potassium (%), in the East region the concentration peaks in Tuffs have been found. The concentrations ranges obtained are preliminary, they characterise the behaviour of this parameter for the Cuban geology, but they do not represent limits for safety assessment purposes yet. Also other factors should be taken into account as the assessment context, time scales and others assumptions before establishing the final concentration limits for the natural radionuclides as a radiological and nuclear safety performance indicator complementary to dose and risk for safety assessment for radiological and nuclear facilities. (author)

  17. The Dread Factor: How Hazards and Safety Training Influence Learning and Performance

    Science.gov (United States)

    Burke, Michael J.; Salvador, Rommel O.; Smith-Crowe, Kristin; Chan-Serafin, Suzanne; Smith, Alexis; Sonesh, Shirley

    2011-01-01

    On the basis of hypotheses derived from social and experiential learning theories, we meta-analytically investigated how safety training and workplace hazards impact the development of safety knowledge and safety performance. The results were consistent with an expected interaction between the level of engagement of safety training and hazardous…

  18. Building patient safety in intensive care nursing : Patient safety culture, team performance and simulation-based training

    OpenAIRE

    Ballangrud, Randi

    2013-01-01

    Aim: The overall aim of the thesis was to investigate patient safety culture, team performance and the use of simulation-based team training for building patient safety in intensive care nursing. Methods: Quantitative and qualitative methods were used. In Study I, 220 RNs from ten ICUs responded to a patient safety culture questionnaire analysed with statistics. Studies II-IV were based on an evaluation of a simulation-based team training programme. Studies II-III included 53 RNs from seven I...

  19. Actual heating energy savings in thermally renovated Dutch dwellings

    International Nuclear Information System (INIS)

    Majcen, Daša; Itard, Laure; Visscher, Henk

    2016-01-01

    The register of the Dutch social housing stock was analysed, containing 300.000 dwellings, renovated between 2010 and 2013. The main objective was twofold: to evaluate the performance gap in these dwellings before and after the renovation and to establish what renovation measures achieve the highest reduction of consumption, particularly in practice (actual savings). The results showed large performance gaps in dwellings with low R and high U values, local heating systems, changes from a non-condensing into a condensing boiler and upgrades to a natural ventilation system. Regarding the actual effectiveness of renovation measures, replacement of old gas boilers with more efficient ones yields the highest energy reduction, followed by deep improvements of windows. Installing mechanical ventilation yields a small reduction compared to other measures, but still much larger than theoretically expected. The paper shows once more that the calculation method currently in use cannot be considered accurate if compared to actual consumption. The study demonstrated that unrealistic theoretical efficiencies of heating systems and insulation values are causing a part of the performance gap. Nowadays, large datasets of buildings thermal performance and actual consumption offer an opportunity to improve these misconceptions. - Highlights: • Performance gap is lower in more efficient buildings. • Replacements of gas boilers – the most energy reduction among renovation measures. • Replacing the ventilation system yields a much larger reduction than expected. • How well are the standard values of the calculation methods defined? • Provide large public building performance databases including actual use data.

  20. Determining the causal relationships among balanced scorecard perspectives on school safety performance: case of Saudi Arabia.

    Science.gov (United States)

    Alolah, Turki; Stewart, Rodney A; Panuwatwanich, Kriengsak; Mohamed, Sherif

    2014-07-01

    In the public schools of many developing countries, numerous accidents and incidents occur because of poor safety regulations and management systems. To improve the educational environment in Saudi Arabia, the Ministry of Education seeks novel approaches to measure school safety performance in order to decrease incidents and accidents. The main objective of this research was to develop a systematic approach for measuring Saudi school safety performance using the balanced scorecard framework philosophy. The evolved third generation balanced scorecard framework is considered to be a suitable and robust framework that captures the system-wide leading and lagging indicators of business performance. The balanced scorecard architecture is ideal for adaptation to complex areas such as safety management where a holistic system evaluation is more effective than traditional compartmentalised approaches. In developing the safety performance balanced scorecard for Saudi schools, the conceptual framework was first developed and peer-reviewed by eighteen Saudi education experts. Next, 200 participants, including teachers, school executives, and Ministry of Education officers, were recruited to rate both the importance and the performance of 79 measurement items used in the framework. Exploratory factor analysis, followed by the confirmatory partial least squares method, was then conducted in order to operationalise the safety performance balanced scorecard, which encapsulates the following five salient perspectives: safety management and leadership; safety learning and training; safety policy, procedures and processes; workforce safety culture; and safety performance. Partial least squares based structural equation modelling was then conducted to reveal five significant relationships between perspectives, namely, safety management and leadership had a significant effect on safety learning and training and safety policy, procedures and processes, both safety learning and training

  1. Regulatory supervision of safety indicators; experience with radiation safety indicators in Dukovany nuclear power plant performance

    International Nuclear Information System (INIS)

    Urbancik, L.; Kulich, V.

    2004-01-01

    The State Office for Nuclear Safety uses three sets of indicators describing the following aspects of a favourable nuclear power plant operation: smooth operation in normal circumstances, low risk to the population, and operation with a positive safety attitude. These are three safety-related areas for assessment. Each area has its own set of indicators. Overall operational safety performance indicators were identified for each attribute. From this point, a level of strategic indicators was developed, and finally, a set of specific indicators was set up. While neither the overall indicators nor the strategic indicators are directly measurable, the specific indicators are directly measurable and are targeted during inspection. (author)

  2. Continuous improvement of the MHTGR safety and competitive performance

    International Nuclear Information System (INIS)

    Eichenberg, T.W.; Etzel, K.T.; Mascaro, L.L.; Rucker, R.A.

    1992-05-01

    An increase in reactor module power from 350 to 450 MW(t) would markedly improve the economics of the Modular High Temperature Gas-Cooled Reactor (MHTGR). The higher power level was recommended as the result of an in-depth cost reduction study undertaken to compete with the declining price of fossil fuel. The safety assessment confirms that the high level of safety, which relies on inherent characteristics and passive features, is maintained at the elevated power level. Preliminary systems, nuclear, and safety performance results are discussed for the recommended 450 MW(t) design. Optimization of plant parameters and design modifications accommodated the operation of the steam generator and circulator at the higher power level. Events in which forced cooling is lost, designated as conduction cooldowns are described in detail. For the depressurized conduction cooldown, without full helium inventory, peak fuel temperatures are significantly lowered. A more negative temperature coefficient of reactivity was achieved while maintaining an adequate fuel cycle and reactivity control. Continual improvement of the MHTGR delivers competitive performance without relinquishing the high safety margins demanded of the next generation of power plants

  3. Performance changes and relationship between vertical jump measures and actual sprint performance in elite sprinters with visual impairment throughout a Parapan American games training season

    Science.gov (United States)

    Loturco, Irineu; Winckler, Ciro; Kobal, Ronaldo; Cal Abad, Cesar C.; Kitamura, Katia; Veríssimo, Amaury W.; Pereira, Lucas A.; Nakamura, Fábio Y.

    2015-01-01

    The aims of this study were to estimate the magnitude of variability and progression in actual competitive and field vertical jump test performances in elite Paralympic sprinters with visual impairment in the year leading up to the 2015 Parapan American Games, and to investigate the relationships between loaded and unloaded vertical jumping test results and actual competitive sprinting performance. Fifteen Brazilian Paralympic sprinters with visual impairment attended seven official competitions (four national, two international and the Parapan American Games 2015) between April 2014 and August 2015, in the 100- and 200-m dash. In addition, they were tested in five different periods using loaded (mean propulsive power [MPP] in jump squat [JS] exercise) and unloaded (squat jump [SJ] height) vertical jumps within the 3 weeks immediately prior to the main competitions. The smallest important effect on performances was calculated as half of the within-athlete race-to-race (or test-to-test) variability and a multiple regression analysis was performed to predict the 100- and 200-m dash performances using the vertical jump test results. Competitive performance was enhanced during the Parapan American Games in comparison to the previous competition averages, overcoming the smallest worthwhile enhancement in both the 100- (0.9%) and 200-m dash (1.43%). In addition, The SJ and JS explained 66% of the performance variance in the competitive results. This study showed that vertical jump tests, in loaded and unloaded conditions, could be good predictors of the athletes' sprinting performance, and that during the Parapan American Games the Brazilian team reached its peak competitive performance. PMID:26594181

  4. Performance changes and relationship between vertical jump measures and actual sprint performance in elite sprinters with visual impairment throughout a Parapan American games training season

    Directory of Open Access Journals (Sweden)

    Irineu eLoturco

    2015-11-01

    Full Text Available The aims of this study were to estimate the magnitude of variability and progression in actual competitive and field vertical jump test performances in elite Paralympic sprinters with visual impairment in the year leading up to the 2015 Parapan American Games, and to investigate the relationships between loaded and unloaded vertical jumping test results and actual competitive sprinting performance. Fifteen Brazilian Paralympic sprinters with visual impairment attended seven official competitions (four national, two international and the Parapan American Games 2015 between April 2014 and August 2015, in the 100- and 200-m dash. In addition, they were tested in five different periods using loaded (mean propulsive power [MPP] in jump squat [JS] exercise and unloaded (squat jump [SJ] height vertical jumps within the 3 weeks immediately prior to the main competitions. The smallest important effect on performances was calculated as half of the within-athlete race-to-race (or test-to-test variability and a multiple regression analysis was performed to predict the 100- and 200-m dash performances using the vertical jump test results. Competitive performance was enhanced during the Parapan American Games in comparison to the previous competition averages, overcoming the smallest worthwhile enhancement in both the 100- (0.9% and 200-m dash (1.43%. In addition, The SJ and JS explained 66% of the performance variance in the competitive results. This study showed that vertical jump tests, in loaded and unloaded conditions, could be good predictors of the athletes’ sprinting performance, and that during the Parapan American Games the Brazilian team reached its peak competitive performance.

  5. Assessment of Human Performance and Safety Culture at the Paks Nuclear Power Plant

    International Nuclear Information System (INIS)

    Toth, Janos; Hadnagy, Lajos

    2002-01-01

    Evaluation of human performance and safety culture of the personnel at a Nuclear Power Plant is a very important element of the self assessment process. At the Paks NPP a systematic approach to this problem started in the early 90's. The first comprehensive analysis of the human performance of the personnel was performed by the Hungarian Research Institute for Electric Power (VEIKI). The analysis of human failures is also a part of the investigation and analysis of safety related reported events. This human performance analysis of events is carried out by the Laboratory of Psychology of the plant and a supporting organisation namely the Department of Ergonomics and Psychology of the Budapest University of Technical and Economical Sciences. The analysis of safety culture at the Paks NPP has been in the focus of attention since the implementation of the INSAG-4 document started world-wide. In 1993 an IAEA model project namely 'Strengthening Training for Operational Safety' was initiated with a sub-project called 'Enhancement of Safety Culture'. Within this project the first step was the initial assessment of the safety culture level at the Paks NPP. It was followed by some corrective actions and safety culture improvement programme. In 1999 the second assessment was performed in order to evaluate the progress as a result of the improvement programme. A few indicators reflecting the elements of safety culture were defined and compared. The assessment of the safety culture with a survey among the managers was performed in September 2000 and the results are being evaluated at the moment. The intention of the plant management is to repeat the assessment every 2-3 years and evaluate the trend of the indicator. (authors)

  6. On the safety performance of the advanced nuclear energy systems

    International Nuclear Information System (INIS)

    Li Shounan

    1999-01-01

    Some features on the safety performances of the Advanced Nuclear Energy Systems are discussed. The advantages and some peculiar problems on the safety of Advanced Nuclear Energy Systems with subcritical nuclear reactor driven by external neutron sources are also pointed out in comparison with conventional nuclear reactors

  7. The relationships between OHS prevention costs, safety performance, employee satisfaction and accident costs.

    Science.gov (United States)

    Bayram, Metin; Ünğan, Mustafa C; Ardıç, Kadir

    2017-06-01

    Little is known about the costs of safety. A literature review conducted for this study indicates there is a lack of survey-based research dealing with the effects of occupational health and safety (OHS) prevention costs. To close this gap in the literature, this study investigates the interwoven relationships between OHS prevention costs, employee satisfaction, OHS performance and accident costs. Data were collected from 159 OHS management system 18001-certified firms operating in Turkey and analyzed through structural equation modeling. The findings indicate that OHS prevention costs have a significant positive effect on safety performance, employee satisfaction and accident costs savings; employee satisfaction has a significant positive effect on accident costs savings; and occupational safety performance has a significant positive effect on employee satisfaction and accident costs savings. Also, the results indicate that safety performance and employee satisfaction leverage the relationship between prevention costs and accident costs.

  8. Analysis of international approaches which are used at development of theoperational safety performance indicators

    International Nuclear Information System (INIS)

    Lyigots'kij, O.Yi.; Nosovs'kij, A.V.; Chemeris, Yi.O.

    2009-01-01

    Description of international approaches and experience of the use of theoperational safety performance indicators system is provided for estimationof current status and making a decision on corrections in the operationpractice. The state of development of the operational safety performanceindicators system by the operating organization is overviewed. Thepossibility of application of international approaches during development ofthe integral safety performance indicators system is analyzed. Aims and tasksof future researches are formulated in relation to development of theintegral safety performance indicators system.

  9. Assessment of softball bat safety performance using mid-compression polyurethane softballs.

    Science.gov (United States)

    McDowell, Mark

    2004-07-01

    There is currently much debate about the safety of the sport of softball. Batted-ball speed and average pitcher reaction time are factors often used to determine safe performance. Batted-ball speed is shown to be the most important factor to consider when determining safe play. Average pitcher reaction time is explained and directly correlated to batted-ball speed. Eleven aluminum multi-wall, three aluminum single-wall and two composite softball bats were tested with mid-compression polyurethane softballs averaging 1721+/-62 N/6.4 mm to represent the relative bat-ball performance for the sport of slowpitch softball. Nine men and six women were chosen for this study out of a test group of over three hundred slowpitch softball players. On average, aluminum bat performance results were within the recommended safety limits established by the national softball associations. However, when composite bats were used, their performance results exceeded the recommended safety limits which can pose a significant safety risk. Using aluminum softball bats, batted-ball speeds ranged from 80 to 145km x h(-1) Using composite softball bats, batted-ball speeds ranged from 146 to 161 km x h(-1). The scientific relevance of this study is to provide performance information that can lead to injury prevention in the sport of softball.

  10. Transient safety performance of the PRISM innovative liquid metal reactor

    International Nuclear Information System (INIS)

    Magee, P.M.; Dubberley, A.E.; Rhow, S.K.; Wu, T.

    1988-01-01

    The PRISM sodium-cooled reactor concept utilizes passive safety characteristics and modularity to increase performance margins, improve licensability, reduce owner's risk and reduce costs. The relatively small size of each reactor module (471 MWt) facilitates the use of passive self-shutdown and shutdown heat removal features, which permit design simplification and reduction of safety-related systems. Key to the transient performance is the inherent negative reactivity feedback characteristics of the core design resulting from the use of metal (U-Pu-Zr) swing, and very low control rod runout worth. Selected beyond design basis events relying only on these core design features are analyzed and the design margins summarized to demonstrate the advancement in reactor safety achieved with the PRISM design concept

  11. Scientific Approach for Optimising Performance, Health and Safety in High-Altitude Observatories

    Science.gov (United States)

    Böcker, Michael; Vogy, Joachim; Nolle-Gösser, Tanja

    2008-09-01

    The ESO coordinated study “Optimising Performance, Health and Safety in High-Altitude Observatories” is based on a psychological approach using a questionnaire for data collection and assessment of high-altitude effects. During 2007 and 2008, data from 28 staff and visitors involved in APEX and ALMA were collected and analysed and the first results of the study are summarised. While there is a lot of information about biomedical changes at high altitude, relatively few studies have focussed on psychological changes, for example with respect to performance of mental tasks, safety consciousness and emotions. Both, biomedical and psychological changes are relevant factors in occupational safety and health. The results of the questionnaire on safety, health and performance issues demonstrate that the working conditions at high altitude are less detrimental than expected.

  12. High Burnup Fuel Performance and Safety Research

    Energy Technology Data Exchange (ETDEWEB)

    Bang, Je Keun; Lee, Chan Bok; Kim, Dae Ho (and others)

    2007-03-15

    The worldwide trend of nuclear fuel development is to develop a high burnup and high performance nuclear fuel with high economies and safety. Because the fuel performance evaluation code, INFRA, has a patent, and the superiority for prediction of fuel performance was proven through the IAEA CRP FUMEX-II program, the INFRA code can be utilized with commercial purpose in the industry. The INFRA code was provided and utilized usefully in the universities and relevant institutes domesticallly and it has been used as a reference code in the industry for the development of the intrinsic fuel rod design code.

  13. Effects of alcohol (BAC 0.5‰) and ecstasy (MDMA 100 mg) on simulated driving performance and traffic safety.

    Science.gov (United States)

    Veldstra, Janet L; Brookhuis, Karel A; de Waard, Dick; Molmans, Barbara H W; Verstraete, Alain G; Skopp, Gisela; Jantos, Ricarda

    2012-08-01

    An increasing number of fatal road-accidents have been reported in which ecstasy was found in the blood of drivers. Although, ecstasy is frequently found to have been used in combination with alcohol, studies on the acute effects of ecstasy co-administered with alcohol on driving performance are relatively rare. The present study was designed to establish the extent of driver impairment as a consequence of ecstasy or combined ecstasy and alcohol use as compared to driving under the influence of 0.3‰, 0.5‰ and 0.8‰ alcohol. Furthermore, subjective performance was also assessed. Alcohol and ecstasy mainly influenced automated driving performance such as lateral and speed control. However, small to no effects of the substances were found on more complex driving behaviour. Overall, variance within the different driving measures was high especially when participants were treated with 3.4-methylenedioxy-methamphetamine (MDMA) and alcohol. Furthermore, equivalence testing showed that combined use may lead to impaired driving for some, but not all, drivers. Participants rated their own performance to be slightly worse than normal in both studies. Since driving was actually seriously deteriorated, this was a falsely positive assessment of their condition. The dissociation between subjective perceptions and objective performance decrements are important notions for traffic safety since this may affect a driver's judgement of whether or not it is safe to drive. For example, an intoxicated individual might decide to drive because the feelings of alertness caused by MDMA cloud the impairing effects of other drugs such as alcohol, thereby creating a potentially serious risk for traffic safety.

  14. Teamwork skills in actual, in situ, and in-center pediatric emergencies: performance levels across settings and perceptions of comparative educational impact.

    Science.gov (United States)

    Couto, Thomaz Bittencourt; Kerrey, Benjamin T; Taylor, Regina G; FitzGerald, Michael; Geis, Gary L

    2015-04-01

    Pediatric emergencies require effective teamwork. These skills are developed and demonstrated in actual emergencies and in simulated environments, including simulation centers (in center) and the real care environment (in situ). Our aims were to compare teamwork performance across these settings and to identify perceived educational strengths and weaknesses between simulated settings. We hypothesized that teamwork performance in actual emergencies and in situ simulations would be higher than for in-center simulations. A retrospective, video-based assessment of teamwork was performed in an academic, pediatric level 1 trauma center, using the Team Emergency Assessment Measure (TEAM) tool (range, 0-44) among emergency department providers (physicians, nurses, respiratory therapists, paramedics, patient care assistants, and pharmacists). A survey-based, cross-sectional assessment was conducted to determine provider perceptions regarding simulation training. One hundred thirty-two videos, 44 from each setting, were reviewed. Mean total TEAM scores were similar and high in all settings (31.2 actual, 31.1 in situ, and 32.3 in-center, P = 0.39). Of 236 providers, 154 (65%) responded to the survey. For teamwork training, in situ simulation was considered more realistic (59% vs. 10%) and more effective (45% vs. 15%) than in-center simulation. In a video-based study in an academic pediatric institution, ratings of teamwork were relatively high among actual resuscitations and 2 simulation settings, substantiating the influence of simulation-based training on instilling a culture of communication and teamwork. On the basis of survey results, providers favored the in situ setting for teamwork training and suggested an expansion of our existing in situ program.

  15. Research on Integration of NPP Operational Safety Management Performance Systems

    International Nuclear Information System (INIS)

    Chi, Miao; Shi, Liping

    2014-01-01

    The operational safety management of Nuclear Power Plants demands systematic planning and integrated control. NPPs are following the well-developed safety indicator systems proposed by IAEA Operational Safety Performance Indicator Programme, NRC Reactor Oversight Process or the other institutions. Integration of the systems is proposed to benefiting from the advantages of both systems and avoiding improper application into the real world. The authors analyzed the possibility and necessity for system integration, and propose an indicator system integrating method

  16. Safety culture as an element of contact and cooperation between utilities, research and safety authorities

    International Nuclear Information System (INIS)

    Hoegberg, L.

    1994-01-01

    The safety culture approach may simply be seen as a recognition of the close interdependence between safety and organisational processes: achievement of technical safety objectives will largely depend on the quality of the implementation processes in the organisations concerned. With a slight modification of the original INSAG formulation, SKI defines safety culture as 'a consciously formulated and implemented set of values in an organisation, which establishes that, as an overriding priority, safety issues receive the attention warranted by their significance'. In practice, a high level of safety culture means the systematic organisation and implementation of a number of activities aimed at creating a high quality defence in depth against both technical and human failures that may cause accidents. An enquiring and learning attitude is a key element of such a safety culture. For example, to prevent accidents, the organisation always needs to be reactive to incidents, by performing proper root cause analysis of both technical and organisational factors, and taking appropriate corrective actions. The long term organisational objective should be to be proactive and identify deficiencies in technology and organisation that may lead to serious incidents or, at worst, accidents and take corrective action even before actual occurrence of incidents of substantial safety significance. (author) 13 refs

  17. Evaluation of safety practices and performance in a brewery industry ...

    African Journals Online (AJOL)

    Evaluation of safety practices and performance in a brewery industry in Nigeria between 2000 – 2007. ... Journal of Applied Sciences and Environmental Management ... The study revealed that a total of 156 accidents were prevented in the period of the safety programme which translates to an average of 19.45 per year.

  18. Transformational leadership and safety performance among nurses: the mediating role of knowledge-related job characteristics.

    Science.gov (United States)

    Lievens, Ilse; Vlerick, Peter

    2014-03-01

    To report the impact of transformational leadership on two dimensions of nurses' safety performance (i.e. safety compliance and safety participation) and to study the mediating role of knowledge-related job characteristics in this relationship. Safety performance refers to the behaviours that employees exhibit to adhere to safety guidelines and to promote health and safety at their workplace. Nurses' safety performance is a major challenge for healthcare settings, urging the need to identify the key determinants and psychological mechanisms that influence it. A cross-sectional survey study. The study was carried out in September 2010 in a large Belgian hospital. We used self-administered questionnaires; 152 nurses participated. The hypotheses were tested using hierarchical regression analyses. In line with our first hypothesis, the results show that transformational leadership exerted a significant positive impact on both dimensions of nurses' safety performance. This positive relation was mediated by knowledge-related job characteristics, supporting our second hypothesis. Head nurses' transformational leadership can enhance nurses' compliance with and participation in safety. Furthermore, transformational head nurses are able to influence the perception that their nurses have about the kind and amount of knowledge in their job, which can also lead to increases in both dimensions of nurses' safety performance. This study therefore demonstrates the key impact that transformational head nurses have, both directly and indirectly, on the safety performance of their nurses. © 2013 John Wiley & Sons Ltd.

  19. The safety climate of a Department of Energy nuclear facility: A sociotechnical analysis

    International Nuclear Information System (INIS)

    Johnson, A.E.; Harbour, J.L.

    1993-01-01

    Government- and public-sponsored groups are increasingly demanding greater accountability by the Department of Energy's weapons complex. Many of these demands have focused on the development of a positive safety climate, one that not only protects workers onsite, but also the surrounding populace and environment as well. These demands are, in part, a response to findings which demonstrate a close linkage between actual organizational safety performance and the organization's safety climate, i.e., the collective attitudes employees hold concerning the level of safety in their organization. This paper describes the approach taken in the systematic assessment of the safety climate at EG ampersand G Rocky Flats Plant (RFP)

  20. Issues affecting advanced passive light-water reactor safety analysis

    International Nuclear Information System (INIS)

    Beelman, R.J.; Fletcher, C.D.; Modro, S.M.

    1992-01-01

    Next generation commercial reactor designs emphasize enhanced safety through improved safety system reliability and performance by means of system simplification and reliance on immutable natural forces for system operation. Simulating the performance of these safety systems will be central to analytical safety evaluation of advanced passive reactor designs. Yet the characteristically small driving forces of these safety systems pose challenging computational problems to current thermal-hydraulic systems analysis codes. Additionally, the safety systems generally interact closely with one another, requiring accurate, integrated simulation of the nuclear steam supply system, engineered safeguards and containment. Furthermore, numerical safety analysis of these advanced passive reactor designs wig necessitate simulation of long-duration, slowly-developing transients compared with current reactor designs. The composite effects of small computational inaccuracies on induced system interactions and perturbations over long periods may well lead to predicted results which are significantly different than would otherwise be expected or might actually occur. Comparisons between the engineered safety features of competing US advanced light water reactor designs and analogous present day reactor designs are examined relative to the adequacy of existing thermal-hydraulic safety codes in predicting the mechanisms of passive safety. Areas where existing codes might require modification, extension or assessment relative to passive safety designs are identified. Conclusions concerning the applicability of these codes to advanced passive light water reactor safety analysis are presented

  1. Test plan for Fauske and Associates to perform tube propagation experiments with simulated Hanford tank wastes

    International Nuclear Information System (INIS)

    Carlson, C.D.; Babad, H.

    1996-05-01

    This test plan, prepared at Pacific Northwest National Laboratory for Westinghouse Hanford Company, provides guidance for performing tube propagation experiments on simulated Hanford tank wastes and on actual tank waste samples. Simulant compositions are defined and an experimental logic tree is provided for Fauske and Associates (FAI) to perform the experiments. From this guidance, methods and equipment for small-scale tube propagation experiments to be performed at the Hanford Site on actual tank samples will be developed. Propagation behavior of wastes will directly support the safety analysis (SARR) for the organic tanks. Tube propagation may be the definitive tool for determining the relative reactivity of the wastes contained in the Hanford tanks. FAI have performed tube propagation studies previously on simple two- and three-component surrogate mixtures. The simulant defined in this test plan more closely represents actual tank composition. Data will be used to support preparation of criteria for determining the relative safety of the organic bearing wastes

  2. Improvements in operational safety performance of the Magnox power stations

    Energy Technology Data Exchange (ETDEWEB)

    Marchese, C.J. [BNFL Magnox Generation, Berkeley (United Kingdom)

    2000-10-01

    In the 43 years since commencement of operation of Calder Hall, the first Magnox power station, there remain eight Magnox stations and 20 reactors still in operation, owned by BNFL Magnox Generation. This paper describes how the operational safety performance of these stations has significantly improved over the last ten years. This has been achieved against a background of commercial competition introduced by privatization and despite the fact that the Magnox base design belongs to the past. Finally, the company's future plans for continued improvements in operational safety performance are discussed. (author)

  3. Operational safety system performance alternative to the WANO's indicator

    International Nuclear Information System (INIS)

    Lyra, Moacir

    2002-01-01

    One of the operational safety performance indicators recommended by the World Association of Nuclear Operators (WANO) and adopted by Electronuclear is the reliability of the safety systems. The parameter selected to represent this indicator is the average unavailability of the trains of the concerned system. This parameter would be universally representative of the reliability for comparison purpose only if all nuclear power plants were designed within the same redundancy criteria. Considering the diversity of design criteria of the power plants in operation and based on a probabilistic approach, this paper proposes new performance indicators which are comparable regardless the redundancy criteria of the system. A case example applied to a system of the Angra 2 nuclear power plant shows that, even though with the plant in the infancy phase, the performance of the system in the period is very good. (author)

  4. Comparing identically designed grayscale (50 phase level) and binary (5 phase levels) splitters: actual versus modeled performance

    Science.gov (United States)

    Lizotte, Todd E.; Ohar, Orest P.; Tuttle, Tracie

    2006-04-01

    Performance of diffractive optics is determined by high-quality design and a suitable fabrication process that can actually realize the design. Engineers who are tasked with developing or implementing a diffractive optic solution into a product need to take into consideration the risks of using grayscale versus binary fabrication processes. In many cases, grayscale design doesn't always provide the best solution or cost benefit during product development. This fabrication dilemma arises when the engineer has to select a source for design and/or fabrication. Engineers come face to face with reality in view of the fact that diffractive optic suppliers tend to provide their services on a "best effort basis". This can be very disheartening to an engineer who is trying to implement diffractive optics. This paper will compare and contrast the design and performance of a 1 to 24 beam, two dimensional; beam splitter fabricated using a fifty (50) phase level grayscale and a five (5) phase level binary fabrication methods. Optical modeling data will be presented showing both designs and the performance expected prior to fabrication. An overview of the optical testing methods used will be discussed including the specific test equipment and metrology techniques used to verify actual optical performance and fabricated dimensional stability of each optical element. Presentation of the two versions of the splitter will include data on fabrication dimensional errors, split beam-to-beam uniformity, split beam-to-beam spatial size uniformity and splitter efficiency as compared to the original intended design performance and models. This is a continuation of work from 2005, Laser Beam Shaping VI.

  5. Experience of Tecnatom in Developing a Strong Leadership for Safety and Performance

    International Nuclear Information System (INIS)

    González, F.; Villadóniga, J. I.

    2016-01-01

    This paper presents experience and insights of Tecnatom in the support of internal and external clients to develop a strong Leadership for Safety. Several cases are presented briefly: (a) The leadership and culture change activities for a utility, a radwaste company, and for Tecnatom itself. One important characteristic of the work performed is the detailed consideration of the underlying organizational culture that underpins the safety culture. Measurable improvements have been achieved and some of the key insights are shared in this paper. (b) The development and implementation of a leadership model with 17 competencies, including safety explicitly. One benefit of this model is that allows to perform a quantitative assessment of leadership effectiveness, something vital to be able to ensure that leadership development actions are truly supporting safety. The model uses an approach to development oriented to strengths and the use of companion competencies to further develop leadership. Moreover it aims to produce significant improvements on safety but also on performance, since both are not competing goals when the proper leadership model is selected. The training material prepared was shortlisted in the 2014 Nuclear Training Awards. (c) The design and implementation of a training development program on Safety Culture, and required competencies of Leadership, for Top Managers of the nuclear industry, as part of the project NUSHARE of the European Commission’s 7th research framework program. The program is sensible to the reduced time availability of Top Managers and uses a combination of learning approaches (webinars, micro-elearnings, web meetings) that provide higher flexibility for the learner, but complemented with other proven methods (group dialog, journaling, mentoring, etc.) to ensure that the program is effective. All these experiences reveal that to improve the organizational Safety Culture we need to enhance Leadership for Safety and Performance

  6. Preliminary study on functional performance of compound type multistage safety injection tank

    International Nuclear Information System (INIS)

    Bae, Youngmin; Kim, Young In; Kim, Keung Koo

    2015-01-01

    Highlights: • Functional performance of compound type multistage safety injection tanks is studied. • Effects of key design parameters are scrutinized. • Distinctive flow features in compound type safety injection tanks are explored. - Abstract: A parametric study is carried out to evaluate the functional performance of a compound type multistage safety injection tank that would be considered one of the components for the passive safety injection systems in nuclear power plants. The effects of key design parameters such as the initial volume fraction and charging pressure of gas, tank elevation, vertical location of a sparger, resistance coefficient, and operating condition on the injection flow rate are scrutinized along with a discussion of the relevant flow features. The obtained results indicate that the compound type multistage safety injection tank can effectively control the injection flow rate in a passive manner, by switching the driving force for the safety injection from gas pressure to gravity during the refill and reflood phases, respectively

  7. Utility Expectations for Human Performance and Safety Culture in the Supplier Community

    International Nuclear Information System (INIS)

    Clewett, L. K.

    2016-01-01

    Canadian NPPs, like many others around the world, make use of suppliers for the design and execution of major projects, and to support on-going inspection and maintenance activities. The work performed by suppliers today represents a significant portion of the work performed at utility NPPs, and, at times, can even exceed the work performed by utility staff. It is imperative for both the utility and the supplier work forces to work in collaboration to ensure that the probability of consequential errors impacting plant safety or contributing to broader enterprise risk is kept very low. An important element for keeping the risk low is for utilities to work with their suppliers to develop a high degree of confidence that the supplier workforce is performing to the same standards of human performance and safety culture as its own staff. This paper will provide a senior utility executive’s expectations and perspective on achieving excellence in supplier human performance and safety culture. (author)

  8. The Argentine Approach to Radiation Safety: Its Ethical Basis

    International Nuclear Information System (INIS)

    Gonzalez, A.J.

    2011-01-01

    The ethical bases of Argentina's radiation safety approach are reviewed. The applied principles are those recommended and established internationally, namely: the principle of justification of decisions that alters the radiation exposure situation; the principle of optimization of protection and safety; the principle of individual protection for restricting possible inequitable outcomes of optimized safety; and the implicit principle of inter generational prudence for protection future generations and the habitat. The principles are compared vis-a-vis the prevalent ethical doctrines: justification vis-a-vis teleology; optimization vis-a-vis utilitarianism; individual protection vis-a-vis de ontology; and, inter generational prudence vis-a-vis aretaicism (or virtuosity). The application of the principles and their ethics in Argentina is analysed. These principles are applied to All exposure to radiation harm; namely, to exposures to actual doses and to exposures to actual risk and potential doses, including those related to the safety of nuclear installations, and they are harmonized and applied in conjunction. It is concluded that building a bridge among all available ethical doctrines and applying it to radiation safety against actual doses and actual risk and potential doses is at the roots of the successful nuclear regulatory experience in Argentina.

  9. Barrier performance researches for the safety evaluation

    International Nuclear Information System (INIS)

    Niibori, Yuichi

    2004-01-01

    So far, many researches were conducted to propose a scientific evidence (a safety case) for the realization of geological disposal in Japan. In order to regulate the geological disposal system of radioactive wastes, on the other hand, we need also a holistic approach to integrate various data related for the performance evaluations of the engineered barrier system and the natural barrier system. However, the scientific bases are not sufficient to establish the safety regulation for such a natural system. For example, we often apply the specific probability density function (PDF) to the uncertainty of barrier system due to the essential heterogeneity. However, the applicability is not clear in the regulation point of view. A viewpoint to understand such an applicability of PDFs has been presented. (author)

  10. Opportunities for Using Building Information Modeling to Improve Worker Safety Performance

    Directory of Open Access Journals (Sweden)

    Kasim Alomari

    2017-02-01

    Full Text Available Building information modelling (BIM enables the creation of a digital representation of a designed facility combined with additional information about the project attributes, performance criteria, and construction process. Users of BIM tools point to the ability to visualize the final design along with the construction process as a beneficial feature of using BIM. Knowing the construction process in relationship to a facility’s design benefits both safety professionals when planning worker safety measures for a project and designers when creating a project’s design. Success in using BIM to enhance safety partly depends on the familiarity of project personnel with BIM tools and the extent to which the tools can be used to identify and eliminate safety hazards. In a separate, ongoing study, the authors investigated the connection between BIM and safety to document the opportunities, barriers, and impacts. Utilizing an on-line survey of project engineers who work for construction firms together with a comprehensive literature review, the study found those who use BIM feel that it aids in communication of project information and project delivery, both of which have been found to have positive impacts on construction site safety. Further, utilizing the survey results, the authors apply the binary logistic regression econometric framework to better understand the factors that lead to safety professionals believing that BIM increases safety in the work place. In addition, according to the survey results, a large percentage of the engineers who use BIM feel that ultimately it helps to eliminate safety hazards and improve worker safety. The study findings suggest that improvements in safety performance across the construction industry may be due in part to increased use of BIM in the construction industry.

  11. Annual health, safety and environmental performance report for 1992

    International Nuclear Information System (INIS)

    Orman, R.F.; Richards, S.

    1993-12-01

    This report summarizes the safety and environmental record of the operations of Atomic Energy of Canada Limited (AECL) during 1992. An introduction highlights the results and describes the facilities and organizational systems. Subsequent sections indicate the performance of the company with respect to personnel radiation exposures, occupational injuries, the handling of wastes and the release of materials into the environment. Programs in health, safety and environmental protection are presented, along with site remediation and emergency preparedness practices

  12. Annual health, safety and environmental performance report for 1992

    International Nuclear Information System (INIS)

    Orman, R.F.; Richards, S.

    1993-12-01

    This report summarizes the safety and environmental record of the operations of Atomic Energy of Canada Limited (AECL) during 1992. an introduction highlights the results and describes the facilities and organizational systems. Subsequent sections indicate the performance of the company with respect to personnel radiation exposures, occupational injuries, the handling of wastes and the release of materials into the environment. Programs in health, safety and environmental protection are presented, along with site remediation and emergency preparedness practices

  13. Regulatory activities in the area of fuel safety and performance

    International Nuclear Information System (INIS)

    Viktorov, A.; Couture, M.

    2005-01-01

    Generic Action Item 94G02 'Impact of Fuel Bundle Condition on Reactor Safety' in many ways determined the present priorities in regulatory activities related to fuel performance. As one of the closure criteria it required that all licensees establish 'an effective formal and systematic process for integrating fuel design, fuel and channel inspection, laboratory examination, research, operating limits and safety analysis'. To date, such a process has been, to a large extent, put in place by all licensees. To assure that such processes remain operational and effective after the GAI closure, CNSC required, through S-99, to report annually on fuel performance and major activities in the fuel safety area. The scope of reported information has been defined to allow CNSC staff evaluation of key events and trends in fuel performance. To compliment reporting by the industry, CNSC staff has conducted targeted inspections of fuel compliance programs at all sites. Combined together, these activities provide the regulator with the confidence that CANDU fuel is robust and operates with safety margins. The scrutiny, to which fuel performance has been subjected lately, has allowed identification of certain programmatic weaknesses and gaps in the knowledge concerning the fuel behaviour under various conditions. It has become apparent that top-level strategies for assessment of fuel performance may have been inadequate and far from systematic; fuel inspection practices and capabilities have varied significantly from site to site; certain issues were identified but remained unaddressed for significant time; priorities in experimental or design support activities were not assigned consistently. The presentation gives examples of areas where, in the opinion of the CNSC staff, further work is required to support fuel design and safety envelopes. The implementation of new CANFLEX fuel designs is currently being considered by the industry and CNSC staff has been engaged in the review

  14. Quantitative assessment of safety barrier performance in the prevention of domino scenarios triggered by fire

    International Nuclear Information System (INIS)

    Landucci, Gabriele; Argenti, Francesca; Tugnoli, Alessandro; Cozzani, Valerio

    2015-01-01

    The evolution of domino scenarios triggered by fire critically depends on the presence and the performance of safety barriers that may have the potential to prevent escalation, delaying or avoiding the heat-up of secondary targets. The aim of the present study is the quantitative assessment of safety barrier performance in preventing the escalation of fired domino scenarios. A LOPA (layer of protection analysis) based methodology, aimed at the definition and quantification of safety barrier performance in the prevention of escalation was developed. Data on the more common types of safety barriers were obtained in order to characterize the effectiveness and probability of failure on demand of relevant safety barriers. The methodology was exemplified with a case study. The results obtained define a procedure for the estimation of safety barrier performance in the prevention of fire escalation in domino scenarios. - Highlights: • We developed a methodology for the quantitative assessment of safety barriers. • We focused on safety barriers aimed at preventing domino effect triggered by fire. • We obtained data on effectiveness and availability of the safety barriers. • The methodology was exemplified with a case study of industrial interest. • The results showed the role of safety barriers in preventing fired domino escalation

  15. Key Factors Affecting Construction Safety Performance in Developing Countries: Evidence from Cambodia

    Directory of Open Access Journals (Sweden)

    Serdar Durdyev

    2017-12-01

    Full Text Available Although proper safety management in construction is of utmost importance; anecdotal evidence suggests that safety is not adequately considered in many developing countries. This paper considers the key variables affecting construction safety performance in Cambodia. Using an empirical questionnaire survey targeting local construction professionals, respondents were invited to rate the level of importance of 30 variables identified from the seminal literature. The data set was subjected to factor analysis. Correlations between the variables show that five key factors underlie the challenges facing the local industry; management and organisation, resources, site management, cosmetic and workforce. It is found that the forefront construction professionals (top management and government authorities should take more responsibilities for further improvements in safety performance on project sites. Findings and recommendations of this study may be useful to construction professional who are seeking ways to improve safety records in developing countries.

  16. Gap Analysis Approach for Construction Safety Program Improvement

    Directory of Open Access Journals (Sweden)

    Thanet Aksorn

    2007-06-01

    Full Text Available To improve construction site safety, emphasis has been placed on the implementation of safety programs. In order to successfully gain from safety programs, factors that affect their improvement need to be studied. Sixteen critical success factors of safety programs were identified from safety literature, and these were validated by safety experts. This study was undertaken by surveying 70 respondents from medium- and large-scale construction projects. It explored the importance and the actual status of critical success factors (CSFs. Gap analysis was used to examine the differences between the importance of these CSFs and their actual status. This study found that the most critical problems characterized by the largest gaps were management support, appropriate supervision, sufficient resource allocation, teamwork, and effective enforcement. Raising these priority factors to satisfactory levels would lead to successful safety programs, thereby minimizing accidents.

  17. Safety assessment in plant layout design using indexing approach: Implementing inherent safety perspective

    International Nuclear Information System (INIS)

    Tugnoli, Alessandro; Khan, Faisal; Amyotte, Paul; Cozzani, Valerio

    2008-01-01

    The design of layout plans requires adequate assessment tools for the quantification of safety performance. The general focus of the present work is to introduce an inherent safety perspective at different points of the layout design process. In particular, index approaches for safety assessment and decision-making in the early stages of layout design are developed and discussed in this two-part contribution. Part 1 (accompanying paper) of the current work presents an integrated index approach for safety assessment of early plant layout. In the present paper (Part 2), an index for evaluation of the hazard related to the potential of domino effects is developed. The index considers the actual consequences of possible escalation scenarios and scores or ranks the subsequent accident propagation potential. The effects of inherent and passive protection measures are also assessed. The result is a rapid quantification of domino hazard potential that can provide substantial support for choices in the early stages of layout design. Additionally, a case study concerning selection among various layout options is presented and analyzed. The case study demonstrates the use and applicability of the indices developed in both parts of the current work and highlights the value of introducing inherent safety features early in layout design

  18. Nuclear criticality safety training: guidelines for DOE contractors

    International Nuclear Information System (INIS)

    Crowell, M.R.

    1983-09-01

    The DOE Order 5480.1A, Chapter V, Safety of Nuclear Facilities, establishes safety procedures and requirements for DOE nuclear facilities. This guide has been developed as an aid to implementing the Chapter V requirements pertaining to nuclear criticality safety training. The guide outlines relevant conceptual knowledge and demonstrated good practices in job performance. It addresses training program operations requirements in the areas of employee evaluations, employee training records, training program evaluations, and training program records. It also suggests appropriate feedback mechanisms for criticality safety training program improvement. The emphasis is on academic rather than hands-on training. This allows a decoupling of these guidelines from specific facilities. It would be unrealistic to dictate a universal program of training because of the wide variation of operations, levels of experience, and work environments among DOE contractors and facilities. Hence, these guidelines do not address the actual implementation of a nuclear criticality safety training program, but rather they outline the general characteristics that should be included

  19. Outline of safety regulations and administrations for commercial nuclear power plants in Japan

    International Nuclear Information System (INIS)

    Kinichi Yamamoto

    1987-01-01

    Outline of safety regulations and administrations for the commercial nuclear power plants in Japan is briefly described. The strict measures for safety assurance are always taken based on the principle of defense-indepth. In the actual procedures of regulatory control, the examinations and inspections shall be performed at each individual step in the stage of applications, and also in the stage of constructions. Thus, those regulatory examinations and inspections shall be performed in detail and carefully, and at the most suitable time; resulting in an effective regulatory control by the Ministry of International Trade and Industry. (author)

  20. A structural equation modelling approach examining the pathways between safety climate, behaviour performance and workplace slipping

    Science.gov (United States)

    Swedler, David I; Verma, Santosh K; Huang, Yueng-Hsiang; Lombardi, David A; Chang, Wen-Ruey; Brennan, Melayne; Courtney, Theodore K

    2015-01-01

    Objective Safety climate has previously been associated with increasing safe workplace behaviours and decreasing occupational injuries. This study seeks to understand the structural relationship between employees’ perceptions of safety climate, performing a safety behaviour (ie, wearing slip-resistant shoes) and risk of slipping in the setting of limited-service restaurants. Methods At baseline, we surveyed 349 employees at 30 restaurants for their perceptions of their safety training and management commitment to safety as well as demographic data. Safety performance was identified as wearing slip-resistant shoes, as measured by direct observation by the study team. We then prospectively collected participants’ hours worked and number of slips weekly for the next 12 weeks. Using a confirmatory factor analysis, we modelled safety climate as a higher order factor composed of previously identified training and management commitment factors. Results The 349 study participants experienced 1075 slips during the 12-week follow-up. Confirmatory factor analysis supported modelling safety climate as a higher order factor composed of safety training and management commitment. In a structural equation model, safety climate indirectly affected prospective risk of slipping through safety performance, but no direct relationship between safety climate and slips was evident. Conclusions Results suggest that safety climate can reduce workplace slips through performance of a safety behaviour as well as suggesting a potential causal mechanism through which safety climate can reduce workplace injuries. Safety climate can be modelled as a higher order factor composed of safety training and management commitment. PMID:25710968

  1. Performance Evaluation of SMART Passive Safety System for Small Break LOCA Using MARS Code

    International Nuclear Information System (INIS)

    Chun, Ji Han; Lee, Guy Hyung; Bae, Kyoo Hwan; Chung, Young Jong; Kim, Keung Koo

    2013-01-01

    SMART has significantly enhanced safety by reducing its core damage frequency to 1/10 that of a conventional nuclear power plant. KAERI is developing a passive safety injection system to replace the active safety injection pump in SMART. It consists of four trains, each of which includes gravity-driven core makeup tank (CMT) and safety injection tank (SIT). This system is required to meet the passive safety performance requirements, i.e., the capability to maintain a safe shutdown condition for a minimum of 72 hours without an AC power supply or operator action in the case of design basis accidents (DBAs). The CMT isolation valve is opened by the low pressurizer pressure signal, and the SIT isolation valve is opened at 2 MPa. Additionally, two stages of automatic depressurization systems are used for rapid depressurization. Preliminary safety analysis of SMART passive safety system in the event of a small-break loss-of-coolant accident (SBLOCA) was performed using MARS code. In this study, the safety analysis results of a guillotine break of safety injection line which was identified as the limiting SBLOCA in SMART are given. The preliminary safety analysis of a SBLOCA for the SMART passive safety system was performed using the MARS code. The analysis results of the most limiting SI line guillotine break showed that the collapsed liquid level inside the core support barrel was maintained sufficiently high above the top of core throughout the transient. This means that the passive safety injection flow from the CMT and SIT causes no core uncovery during the 72 hours following the break with no AC power supply or operator action, which in turn results in a consistent decrease in the fuel cladding temperature. Therefore, the SMART passive safety system can meet the passive safety performance requirement of maintaining the plant at a safe shutdown condition for a minimum of 72 hours without AC power or operator action for a representing accident of SBLOCA

  2. A reliability program approach to operational safety

    International Nuclear Information System (INIS)

    Mueller, C.J.; Bezella, W.A.

    1985-01-01

    A Reliability Program (RP) model based on proven reliability techniques is being formulated for potential application in the nuclear power industry. Methods employed under NASA and military direction, commercial airline and related FAA programs were surveyed and a review of current nuclear risk-dominant issues conducted. The need for a reliability approach to address dependent system failures, operating and emergency procedures and human performance, and develop a plant-specific performance data base for safety decision making is demonstrated. Current research has concentrated on developing a Reliability Program approach for the operating phase of a nuclear plant's lifecycle. The approach incorporates performance monitoring and evaluation activities with dedicated tasks that integrate these activities with operation, surveillance, and maintenance of the plant. The detection, root-cause evaluation and before-the-fact correction of incipient or actual systems failures as a mechanism for maintaining plant safety is a major objective of the Reliability Program. (orig./HP)

  3. Fatigue status assessment for reactor pressure vessel based on actual operational transient

    International Nuclear Information System (INIS)

    Zhu Guangqiang; Liao Changbin; Dai Bing; Gui Chun

    2013-01-01

    Background: Fatigue is an important aging mechanism in RPV and it must be contained to aging management working range. Purpose: In order to ensure the safety operation of nuclear power plants, as extension of RPV service time, it is necessary to assess the fatigue damage caused by actual operation transient. Methods: Based on monitoring data of actual operation during the past eleven years, refer to design transient, the statistic analysis for types and occurrence times of actual transient is carried out, at the same time, every transients are combined as different operation cycles and the temperature field and stress field of typical components are analyzed by FEM. Results: Based on these information, fatigue analysis and assessment are finished, if later-actual transients are similar with the previous transients, the calculation result shows that the ratio between maximum of cumulative usage factors and design calculation value is 0.4967 the design transients is conservative. Conclusions: Fatigue status of RPV could be assessed and traced quickly through fatigue status assessment method in this paper based on actual operational transient and assessment result would be a good reference for RPV aging management. (authors)

  4. Performance and safety analysis of WP-cave concept

    International Nuclear Information System (INIS)

    Skagius, K.; Svemar, C.

    1989-08-01

    The report presents a performance safety, and cost analysis of the WP-cave, WPC, concept. In the performance analysis, questions specific to the WPC have been addressed which have been identified to require more detailed studies. Based on the outcome of this analysis, a safety analysis has been made which comprises of the modeling and calculation of radionuclide transport from the repository to the biosphere and the resulting dose exposure to man. The result of the safety analysis indicates that the present design of a WPC repository may give unacceptably high doses. By improving the properties of the bentonite/sand barrier such that the hydraulic conductivity is reduced, or by changing the short-lived steel canisters to more long-lived canisters, e.g. copper canisters, it is judged possible to achieve a sufficiently low level of dose exposure rates to man. The cost for a WPC repository of the studied design is significantly higher than for a KBS-3 repository considering the Swedish conditions and the Swedish amount of spent fuel. The major costs are connected to the excavation and backfilling of the bentonite/sand barrier. The potential for cost savings is high but it is not judged possible to account for savings in such a way that the WPC concept shows lower cost than the KBS-3 concept. (34 figs., 33 tabs., 29 refs.)

  5. Annual health, safety and environmental performance report for 1993

    Energy Technology Data Exchange (ETDEWEB)

    Gallapher, J D; Wright, M G

    1994-05-01

    This report summarizes the occupational health and safety and the environmental protection record of the operations of Atomic Energy of Canada Limited (AECL) during 1993. An introduction highlights the results and describes the facilities and organizational systems. Subsequent sections indicate the performance of the company with respect to personnel radiation exposures, occupational injuries, the handling of wastes, and the release of materials into the environment. Programs in health, safety and environmental protection are presented, along with site remediation and emergency preparedness practices. (author). 14 figs.

  6. Annual health, safety and environmental performance report for 1993

    International Nuclear Information System (INIS)

    Gallapher, J.D.; Wright, M.G.

    1994-05-01

    This report summarizes the occupational health and safety and the environmental protection record of the operations of Atomic Energy of Canada Limited (AECL) during 1993. An introduction highlights the results and describes the facilities and organizational systems. Subsequent sections indicate the performance of the company with respect to personnel radiation exposures, occupational injuries, the handling of wastes, and the release of materials into the environment. Programs in health, safety and environmental protection are presented, along with site remediation and emergency preparedness practices. (author). 14 figs

  7. Safety indicators: an efficient tool for a better safety

    International Nuclear Information System (INIS)

    Aufort, P.; Lars, R.

    1993-01-01

    Safety indicators based on the examination of the Operating Technical Specifications have been defined with the aim of following the in-operation safety level of French nuclear power plants. These safety indicators are operation feedback tools which permit the a posteriori justification and the adjustment of actual procedures. They would allow detection of an abnormal unavailability occurrence rate or a situation revealing a potential safety problem. So, data acquisition, processing, analysis and display software allowing trend analysis of these indicators has been developed so far as: a reflexion tool for the power plant operators about the safety instructions and the adjustment of preventive maintenance, and a help for decision making at a national level for the examination and the improvement of Operating Technical Specifications. This paper presents the objectives of these safety indicators, the processing tool associated, the preliminary results obtained and more elaborate processing of these indicators. These safety indicators may be very useful in framing probabilistic safety assessments. (author)

  8. Multilevel model of safety climate for furniture industries.

    Science.gov (United States)

    Rodrigues, Matilde A; Arezes, Pedro M; Leão, Celina P

    2015-01-01

    Furniture companies can analyze their safety status using quantitative measures. However, the data needed are not always available and the number of accidents is under-reported. Safety climate scales may be an alternative. However, there are no validated Portuguese scales that account for the specific attributes of the furniture sector. The current study aims to develop and validate an instrument that uses a multilevel structure to measure the safety climate of the Portuguese furniture industry. The Safety Climate in Wood Industries (SCWI) model was developed and applied to the safety climate analysis using three different scales: organizational, group and individual. A multilevel exploratory factor analysis was performed to analyze the factorial structure. The studied companies' safety conditions were also analyzed. Different factorial structures were found between and within levels. In general, the results show the presence of a group-level safety climate. The scores of safety climates are directly and positively related to companies' safety conditions; the organizational scale is the one that best reflects the actual safety conditions. The SCWI instrument allows for the identification of different safety climates in groups that comprise the same furniture company and it seems to reflect those groups' safety conditions. The study also demonstrates the need for a multilevel analysis of the studied instrument.

  9. A performance improvement plan to increase nurse adherence to use of medication safety software.

    Science.gov (United States)

    Gavriloff, Carrie

    2012-08-01

    Nurses can protect patients receiving intravenous (IV) medication by using medication safety software to program "smart" pumps to administer IV medications. After a patient safety event identified inconsistent use of medication safety software by nurses, a performance improvement team implemented the Deming Cycle performance improvement methodology. The combined use of improved direct care nurse communication, programming strategies, staff education, medication safety champions, adherence monitoring, and technology acquisition resulted in a statistically significant (p < .001) increase in nurse adherence to using medication safety software from 28% to above 85%, exceeding national benchmark adherence rates (Cohen, Cooke, Husch & Woodley, 2007; Carefusion, 2011). Copyright © 2012 Elsevier Inc. All rights reserved.

  10. Space Biology and Medicine. Volume 4; Health, Performance, and Safety of Space Crews

    Science.gov (United States)

    Dietlein, Lawrence F. (Editor); Pestov, Igor D. (Editor)

    2004-01-01

    Volume IV is devoted to examining the medical and associated organizational measures used to maintain the health of space crews and to support their performance before, during, and after space flight. These measures, collectively known as the medical flight support system, are important contributors to the safety and success of space flight. The contributions of space hardware and the spacecraft environment to flight safety and mission success are covered in previous volumes of the Space Biology and Medicine series. In Volume IV, we address means of improving the reliability of people who are required to function in the unfamiliar environment of space flight as well as the importance of those who support the crew. Please note that the extensive collaboration between Russian and American teams for this volume of work resulted in a timeframe of publication longer than originally anticipated. Therefore, new research or insights may have emerged since the authors composed their chapters and references. This volume includes a list of authors' names and addresses should readers seek specifics on new information. At least three groups of factors act to perturb human physiological homeostasis during space flight. All have significant influence on health, psychological, and emotional status, tolerance, and work capacity. The first and most important of these factors is weightlessness, the most specific and radical change in the ambient environment; it causes a variety of functional and structural changes in human physiology. The second group of factors precludes the constraints associated with living in the sealed, confined environment of spacecraft. Although these factors are not unique to space flight, the limitations they entail in terms of an uncomfortable environment can diminish the well-being and performance of crewmembers in space. The third group of factors includes the occupational and social factors associated with the difficult, critical nature of the

  11. Fire-safety engineering and performance-based codes

    DEFF Research Database (Denmark)

    Sørensen, Lars Schiøtt

    project administrators, etc. The book deals with the following topics: • Historical presentation on the subject of fire • Legislation and building project administration • European fire standardization • Passive and active fire protection • Performance-based Codes • Fire-safety Engineering • Fundamental......Fire-safety Engineering is written as a textbook for Engineering students at universities and other institutions of higher education that teach in the area of fire. The book can also be used as a work of reference for consulting engineers, Building product manufacturers, contractors, building...... thermodynamics • Heat exchange during the fire process • Skin burns • Burning rate, energy release rate and design fires • Proposal to Risk-based design fires • Proposal to a Fire scale • Material ignition and flame spread • Fire dynamics in buildings • Combustion products and toxic gases • Smoke inhalation...

  12. Associations between safety climate and safety management practices in the construction industry.

    Science.gov (United States)

    Marín, Luz S; Lipscomb, Hester; Cifuentes, Manuel; Punnett, Laura

    2017-06-01

    Safety climate, a group-level measure of workers' perceptions regarding management's safety priorities, has been suggested as a key predictor of safety outcomes. However, its relationship with actual injury rates is inconsistent. We posit that safety climate may instead be a parallel outcome of workplace safety practices, rather than a determinant of workers' safety behaviors or outcomes. Using a sample of 25 commercial construction companies in Colombia, selected by injury rate stratum (high, medium, low), we examined the relationship between workers' safety climate perceptions and safety management practices (SMPs) reported by safety officers. Workers' perceptions of safety climate were independent of their own company's implementation of SMPs, as measured here, and its injury rates. However, injury rates were negatively related to the implementation of SMPs. Safety management practices may be more important than workers' perceptions of safety climate as direct predictors of injury rates. © 2017 Wiley Periodicals, Inc.

  13. Modern diaper performance: construction, materials, and safety review.

    Science.gov (United States)

    Dey, Swatee; Kenneally, Dianna; Odio, Mauricio; Hatzopoulos, Ioannis

    2016-07-01

    A review of the literature on diapers and diaper rash reveals that many clinicians are unfamiliar with modern diaper construction and materials as well as diaper safety testing methods. Typical modern diapers do not contain ingredients of concern such as latex and disperse dyes, but use ingredients such as spandex and pigments with a favorable safety profile. Today's disposable diaper is a high performance product whose carefully designed layers and liners provide optimal urine and feces absorption and an ever more clothing-like and comfortable fit. This is possible due to a variety of specialized polymer materials that provide optimal absorption of urine and feces, thereby minimizing skin exposure. © 2016 The International Society of Dermatology.

  14. A structural equation modelling approach examining the pathways between safety climate, behaviour performance and workplace slipping.

    Science.gov (United States)

    Swedler, David I; Verma, Santosh K; Huang, Yueng-Hsiang; Lombardi, David A; Chang, Wen-Ruey; Brennan, Melayne; Courtney, Theodore K

    2015-07-01

    Safety climate has previously been associated with increasing safe workplace behaviours and decreasing occupational injuries. This study seeks to understand the structural relationship between employees' perceptions of safety climate, performing a safety behaviour (ie, wearing slip-resistant shoes) and risk of slipping in the setting of limited-service restaurants. At baseline, we surveyed 349 employees at 30 restaurants for their perceptions of their safety training and management commitment to safety as well as demographic data. Safety performance was identified as wearing slip-resistant shoes, as measured by direct observation by the study team. We then prospectively collected participants' hours worked and number of slips weekly for the next 12 weeks. Using a confirmatory factor analysis, we modelled safety climate as a higher order factor composed of previously identified training and management commitment factors. The 349 study participants experienced 1075 slips during the 12-week follow-up. Confirmatory factor analysis supported modelling safety climate as a higher order factor composed of safety training and management commitment. In a structural equation model, safety climate indirectly affected prospective risk of slipping through safety performance, but no direct relationship between safety climate and slips was evident. Results suggest that safety climate can reduce workplace slips through performance of a safety behaviour as well as suggesting a potential causal mechanism through which safety climate can reduce workplace injuries. Safety climate can be modelled as a higher order factor composed of safety training and management commitment. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

  15. Present condition of survey research on actualization strategy of fast breeding reactor (FBR) cycling. General outlines on the research

    International Nuclear Information System (INIS)

    Hara, Hideaki

    2001-01-01

    The Japan Nuclear Cycle Development Institute (JNC) started the survey research on actualization strategy of FBR cycling under cooperation of related organizations such as electric business company and so on, on July, 1999. The research aims at preparation of technical system to establish the FBR cycling for a future main energy supply source by extracting an actualization picture maximum activated advantages originally haven by the FBR cycling and by proposing a developmental strategy flexibly responsible to diverse needs in future society. Here was reported on effort state of its phase 1 (two years between 1999 and 2000 fiscal years). In the phase 1, it was planned to perform research and development shown as follows: 1) Extraction of actualization candidate concept on the FBR cycling under a premise of safety security and a viewpoint of evaluation on economics, resource effective usage, environmental loading reduction, and nuclear dispersion resistance by conducting investigation and evaluation of wide technical choices adopting innovative techniques, and 2) Embodiment of a research and development program of phase 2 (from 2001 to 2005 fiscal years) by investigating some technical subjects important for selection of research and development program aiming at actualization and its candidate concept on the FBR cycling. (G.K.)

  16. CANDU reactor experience: fuel performance

    International Nuclear Information System (INIS)

    Truant, P.T.; Hastings, I.J.

    1985-07-01

    Ontario Hydro has more than 126 reactor-years experience in operating CANDU reactors. Fuel performance has been excellent with 47 000 channel fuelling operations successfully completed and 99.9 percent of the more than 380 000 bundles irradiated operating as designed. Fuel performance limits and fuel defects have had a negligible effect on station safety, reliability, the environment and cost. The actual incapability charged to fuel is less than 0.1 percent over the stations' lifetimes, and more recently has been zero

  17. Health and safety plan for operations performed for the Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Trippet, W.A. II (IT Corp., (United States)); Reneau, M.; Morton, S.L. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

    1992-04-01

    This document constitutes the generic health and safety plan for the Environmental Restoration Program (ERP). It addresses the health and safety requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); Occupational Safety and Health Administration (OSHA) 29 CFR 1910.120 standard; and EG G Idaho, Inc. This plan is a guide to individuals who must complete a health and safety plan for a task performed for the EPR. It contains a task specific addendum that, when completed, specifically addresses task specific health and safety issues. This health and safety plan reduces the time it takes to write a task specific health and safety plan by providing discussions of requirements, guidance on where specific information is located, and specific topics in the Addendum that must be discussed at a task level. This format encourages a complete task specific health and safety plan and a standard for all health and safety plans written for ERP.

  18. Health and safety plan for operations performed for the Environmental Restoration Program

    International Nuclear Information System (INIS)

    Trippet, W.A. II; Reneau, M.; Morton, S.L.

    1992-04-01

    This document constitutes the generic health and safety plan for the Environmental Restoration Program (ERP). It addresses the health and safety requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); Occupational Safety and Health Administration (OSHA) 29 CFR 1910.120 standard; and EG ampersand G Idaho, Inc. This plan is a guide to individuals who must complete a health and safety plan for a task performed for the EPR. It contains a task specific addendum that, when completed, specifically addresses task specific health and safety issues. This health and safety plan reduces the time it takes to write a task specific health and safety plan by providing discussions of requirements, guidance on where specific information is located, and specific topics in the Addendum that must be discussed at a task level. This format encourages a complete task specific health and safety plan and a standard for all health and safety plans written for ERP

  19. Key Factors Affecting Construction Safety Performance in Developing Countries: Evidence from Cambodia

    OpenAIRE

    Durdyev, Serdar; Mohamed, Sherif; Lay, Meng Leang; Ismail, Syuhaida

    2017-01-01

    Although proper safety management in construction is of utmost importance; anecdotal evidence suggests that safety is not adequately considered in many developing countries. This paper considers the key variables affecting construction safety performance in Cambodia. Using an empirical questionnaire survey targeting local construction professionals, respondents were invited to rate the level of importance of 30 variables identified from the seminal literature. The data set was subjected to f...

  20. International conference on the operational safety performance in nuclear installations. Contributed papers

    International Nuclear Information System (INIS)

    2005-01-01

    In 2001, the IAEA organized an 'International Conference on Topical Issues in Nuclear Safety'. The issues discussed during the conference were: (1) risk- informed decision-making; (2) influence of external factors on safety; (3) safety of fuel cycle facilities; (4) safety of research reactors; and (5) safety performance indicators. Senior nuclear safety decision makers reviewed the issues and formulated recommendations for future actions by national and international organizations. In 2004, the IAEA organized an 'International Conference on Topical Issues in Nuclear Safety' in Beijing China. The issues discussed during the conference were: (1) changing environment - coping with diversity and globalization; (2) operating experience - managing changes effectively; (3) regulatory management systems - adapting to changes in the environment; and (4) long term operations - maintaining safety margins while extending plant lifetimes. The results of this conference confirmed the importance of operators and regulators of nuclear facilities meeting periodically to share experience and opinion on emerging issues and future challenges of the nuclear industry. Substantial progress has been made, and continues to be made by Member States in enhancing the safety of nuclear installations worldwide. At the same time, more attention is being given to other areas of nuclear safety. The safety standards for research reactors are being updated and new standards are planned on the safety of other facilities in the nuclear fuel cycle. The Agency has taken a lead role in this effort and is receiving much support from its Member States to gain international consensus in these areas. The objective of the conference is to foster the exchange of information on operational safety performance and operating experience in nuclear installations, with the aim of consolidating an international consensus on: - the present status of these issues; - emerging issues with international implications

  1. The Role of Leadership in Safety Performance and Results

    Science.gov (United States)

    Caravello, Halina E.

    Employee injury rates in U.S. land-based operations in the energy industry are 2 to 3 times higher relative to other regions in the world. Although a rich literature exists on drivers of safety performance, no previous studies investigated factors influencing this elevated rate. Leadership has been identified as a key contributor to safety outcomes and this grounded theory study drew upon the full range leadership model, situational leadership, and leader-member exchange theories for the conceptual framework. Leadership aspects influencing safety performance were investigated through guided interviews of 27 study participants; data analyses included open and axial coding, and constant comparisons identified higher-level categories. Selective coding integrated categories into the theoretical framework that developed the idealized, transformational leader traits motivating safe behaviors of leading by example, expressing care and concern for employees' well-being, celebrating successes, and communicating the importance of safety (other elements included visibility and commitment). Employee and supervisor participants reported similar views on the idealized leader traits, but low levels of these qualities may be driving elevated injury rates. Identifying these key elements provides the foundation to creating strategies and action plans enabling energy sector companies to prevent employee injuries and fatalities in an industry where tens of thousands of employees are subjected to significant hazards and elevated risks. Creating safer workplaces for U.S. employees by enhancing leaders' skills, building knowledge, and improving behaviors will improve the employees' and their families' lives by reducing the pain and suffering resulting from injuries and fatalities.

  2. Neutronics performances study of silicon carbide as an inert matrix to achieve very high burn-up for light water reactor fuels

    International Nuclear Information System (INIS)

    Chabert, C.; Coulon-Picard, E.; Pelletier, M.

    2007-01-01

    In order to extend the actual limits of light water reactors, the Cea has put emphasis on the exploration of major fuel innovations that would allow us to increase the competitiveness, the safety and flexibility, while keeping the standard PWR environment. Different fuel concepts have been chosen and are actually studied to evaluate their advantages and drawbacks. The objectives of these new fuels are to increase the safety performances and to achieve a very high burn-up. One concept is a CERCER fuel with silicon carbide (SiC) as an inert matrix devoted to reduce the fuel temperature at nominal conditions. Besides the investigation of the neutronic performance, analyses on the thermomechanical performances, the fuel fabrication, the fuel reprocessing and economic aspects have been performed. This paper presents particularly neutronic results obtained for the CERCER fuel. The results show that a very high burn-up, a high safety performance and a better competitiveness cannot be achieved with this fuel concept. (authors)

  3. Organizational Culture and Safety Performance in the Manufacturing Companies in Malaysia: A Conceptual Analysis

    OpenAIRE

    Ong Choon Hee; Lim Lee Ping

    2014-01-01

    The purpose of this paper is to provide a conceptual analysis of organizational culture and safety performance in the manufacturing companies in Malaysia. Our conceptual analysis suggests that manufacturing companies that adopt group culture or hierarchical culture are more likely to demonstrate safety compliance and safety participation. Manufacturing companies that adopt rational culture or developmental culture are less likely to demonstrate safety compliance and safety participation. Give...

  4. Actual questions in Slovak and European nuclear sector

    International Nuclear Information System (INIS)

    Slugen, V.

    2010-01-01

    The close cohesion of research and education underlines the development of all research areas and contributes to their sustainability. In the paper, new approaches of European Commission (DG RTD Energy) to nuclear power engineering development (focused on area fission and reactor systems) and applications also for Slovak conditions are discussed in details. Research, education and training increase not only economical factor and technical development, but imply the higher level of safety culture by design or operation of nuclear installations. The paper will be focused on the actual questions in frame of Slovak as well as European nuclear sector.

  5. Removing unreasonable conservatisms in DOE safety analysis

    International Nuclear Information System (INIS)

    BISHOP, G.E.

    1999-01-01

    While nuclear safety analyses must always be conservative, invoking excessive conservatisms does not provide additional margins of safety. Rather, beyond a fairly narrow point, conservatisms skew a facility's true safety envelope by exaggerating risks and creating unreasonable bounds on what is required for safety. The conservatism has itself become unreasonable. A thorough review of the assumptions and methodologies contained in a facility's safety analysis can provide substantial reward, reducing both construction and operational costs without compromising actual safety

  6. Study on the operational safety performance indicator of nuclear power plants in China

    International Nuclear Information System (INIS)

    Zhou Shirong

    2005-01-01

    The operational Safety Performance Indicator system (SPI) has been more and more regarded recently for their clear and effective characteristic in safety assessment for Nuclear Power Plants (NPPs). A large developing plan for NPPs construction is being discussed and considered in P.R. China. As one of important nuclear country, China expects to ensure the normal operation of NPPs and improve the safety level. National Nuclear Safety Administration (NNSA), National Nuclear Regulatory Agency of China, has put high attention on safety and SPI area, and many endeavours and attempts have been done or being carried out for an establishment of SPI system in China. NNSA intends to build an integrated SPI system to monitor all of the NPPs operation in China, based on the SPI system currently used in the world. NNSA believes that the SPI system will help to more effectively enforce the function of surveillance and management. The paper will introduces the status of study on the operational safety performance indicator of Nuclear Power Plants in China. (author)

  7. Job hindrances, job resources, and safety performance: The mediating role of job engagement.

    Science.gov (United States)

    Yuan, Zhenyu; Li, Yongjuan; Tetrick, Lois E

    2015-11-01

    Job engagement has received widespread attention in organizational research but has rarely been empirically investigated in the context of safety. In the present study, we examined the mediating role of job engagement in the relationships between job characteristics and safety performance using self-reported data collected at a coal mining company in China. Most of our study hypotheses were supported. Job engagement partially mediated the relationships between job resources and safety performance dimensions. Theoretical and practical implications and directions for future research are also discussed. Copyright © 2015 Elsevier Ltd and The Ergonomics Society. All rights reserved.

  8. Physician job satisfaction related to actual and preferred job size

    OpenAIRE

    Schmit Jongbloed, Lodewijk J.; Cohen-Schotanus, Janke; Borleffs, Jan C. C.; Stewart, Roy E.; Schonrock-Adema, Johanna

    2017-01-01

    Background: Job satisfaction is essential for physicians' well-being and patient care. The work ethic of long days and hard work that has been advocated for decades is acknowledged as a threat for physicians' job satisfaction, well-being, and patient safety. Our aim was to determine the actual and preferred job size of physicians and to investigate how these and the differences between them influence physicians' job satisfaction. Method: Data were retrieved from a larger, longitudinal study a...

  9. Electrochemical performance and safety features of high-safety lithium ion battery using novel branched additive for internal short protection

    International Nuclear Information System (INIS)

    Li Yuhan; Lee, Meng-Lun; Wang Fuming; Yang, Chang-Rung; Chu, Peter P.J.; Yau, Shueh-Lin; Pan, Jing-Pin

    2012-01-01

    Highlights: ► N-phenylmaleimide-containing branched oligomer has been employed as an additive in lithium cells. ► The branched oligomer additive enhances safety and cycling performance of Li ion battery. ► The highest temperature of branched oligomer-containing battery was only 85 °C in the nail penetration test. - Abstract: In this study, we have investigated N-phenylmaleimide/bismaleimide-containing branched oligomer (BO1) as additive in Li-ion batteries to increase the safety performance by reducing the probability of batteries suffering an internal short circuit. In the nail penetration test, a LiCoO 2 /MCMB full battery with N-phenylmaleimide/bismaleimide-containing branched oligomer (BO1) showed a significant improvement in thermal stability and was able to restrain the temperature of the battery at about 85 °C. Furthermore, we found that N-phenylmaleimide/bismaleimide-containing branched oligomer (BO1) contained battery revealed better cycling and electrochemical performance, compared with the battery with bismaleimide-containing branched oligomer (BO3) in the electrolyte. The improvement might result from the favorable ionic conductivity, Li ion mobility and lower resistance in the battery. This additive can meet the cycling performance and safety requirements for Li-ion batteries.

  10. Evaluating Models of Human Performance: Safety-Critical Systems Applications

    Science.gov (United States)

    Feary, Michael S.

    2012-01-01

    This presentation is part of panel discussion on Evaluating Models of Human Performance. The purpose of this panel is to discuss the increasing use of models in the world today and specifically focus on how to describe and evaluate models of human performance. My presentation will focus on discussions of generating distributions of performance, and the evaluation of different strategies for humans performing tasks with mixed initiative (Human-Automation) systems. I will also discuss issues with how to provide Human Performance modeling data to support decisions on acceptability and tradeoffs in the design of safety critical systems. I will conclude with challenges for the future.

  11. Key Element Performance In Occupational Safety And Health Management System In Organization (A Literature

    Directory of Open Access Journals (Sweden)

    Agus Salim Nuzaihan Aras

    2016-01-01

    Full Text Available Setting an effective safety and health management system is crucial in order to reduce problem relating to accident and ill in management organizational. It is involve with multiple level of management and stakeholders who empower the organization to the management in handling the safety and health cases and issues in organizational. It is necessary to prepare a well knowledge about safety and health management systems and preparing the framework for setting a certain scale in measuring its performance in this area. The successful or failure of management does showing the capability of the organization in delivering the responsible to management levels [1]. The problem in safe work issues and practices cause by the management commitment and involvement that create improper safety program and procedures, and this crisis keep continuing till present [2]. This paper describes about key element of safety and health management system and measuring the performance in order to get an effective management system in organization that describes the process in achieving effectiveness in management. The literature review will be conducted through the data collection from research findings and defined the strong character of key element in which focusing on measuring performance. A guide on key element performance in occupational safety and health management system is specifically drawn to prepare for a future research.

  12. The actuality and discussion for the data management of radiation sources

    International Nuclear Information System (INIS)

    Yang Yaoyun; Huang Chaoyun; Wang Xiaofeng; Chen Dongliang; Fu Jie

    2008-01-01

    Large amounts of data and information in radiation safety license permits, supervision and inspection have been accumulated in China. Data management of radiation sources is an important aspect of radiation sources security. This paper introduces the main elements, tache and actuality of data management, the strengths and weaknesses of RAIS system in use. This paper analyzes and discusses the approach of establishing radiation sources monitoring information system network. (authors)

  13. Understanding the relationship between safety culture dimensions and safety performance of construction projects through partial least square method

    Science.gov (United States)

    Latief, Yusuf; Machfudiyanto, Rossy A.; Arifuddin, Rosmariani; Yogiswara, Yoko

    2017-03-01

    Based on the data, 32% of accidental cases in Indonesia occurs on constructional sectors. It is supported by the data from Public Work and Housing Department that 27.43% of the implementation level of Safety Management System policy at construction companies in Indonesia remains unsafe categories. Moreover, there are dimensions of occupational safety culture formed including leadership, behavior, strategy, policy, process, people, safety cost, value and contract system. The aim of this study is to determine the model of an effective safety culture and know the relationship between dimensions in construction industry. The method used in this research was questionnaire survey which was distributed to the sample of construction companies either in a national private one in Indonesia. The result of this research is supposed to be able to illustrate the development of the relationship among occupational safety culture dimensions which have influences to the performances of constructional companies in Indonesia.

  14. Seismic performance assessment of base-isolated safety-related nuclear structures

    Science.gov (United States)

    Huang, Y.-N.; Whittaker, A.S.; Luco, N.

    2010-01-01

    Seismic or base isolation is a proven technology for reducing the effects of earthquake shaking on buildings, bridges and infrastructure. The benefit of base isolation has been presented in terms of reduced accelerations and drifts on superstructure components but never quantified in terms of either a percentage reduction in seismic loss (or percentage increase in safety) or the probability of an unacceptable performance. Herein, we quantify the benefits of base isolation in terms of increased safety (or smaller loss) by comparing the safety of a sample conventional and base-isolated nuclear power plant (NPP) located in the Eastern U.S. Scenario- and time-based assessments are performed using a new methodology. Three base isolation systems are considered, namely, (1) Friction Pendulum??? bearings, (2) lead-rubber bearings and (3) low-damping rubber bearings together with linear viscous dampers. Unacceptable performance is defined by the failure of key secondary systems because these systems represent much of the investment in a new build power plant and ensure the safe operation of the plant. For the scenario-based assessments, the probability of unacceptable performance is computed for an earthquake with a magnitude of 5.3 at a distance 7.5 km from the plant. For the time-based assessments, the annual frequency of unacceptable performance is computed considering all potential earthquakes that may occur. For both assessments, the implementation of base isolation reduces the probability of unacceptable performance by approximately four orders of magnitude for the same NPP superstructure and secondary systems. The increase in NPP construction cost associated with the installation of seismic isolators can be offset by substantially reducing the required seismic strength of secondary components and systems and potentially eliminating the need to seismically qualify many secondary components and systems. ?? 2010 John Wiley & Sons, Ltd.

  15. Promotion of good safety culture at a Canadian HWR

    International Nuclear Information System (INIS)

    Curle, B.

    1996-01-01

    People work at a nuclear plant within a structured environment. It is the programs, procedures and other ''tools'' that are used in the workplace that actually guide behaviours, and behaviours then guide performance. The safety culture in the workplace is ''the way we do things around here''. This culture is created by structures, behaviours and performance, and is characterized by three attributes: A questioning attitude; a rigorous and prudent approach; open 2-way communication. This paper discusses a model of safety culture which puts the operating experience or learning cycle program at the heart of the endeavor. This cycle also consists of three elements: Observation; reporting; learning. It is more of a theoretical paper than a report of success at this stage. However, the ideas presented are being used to design and implement a strong safety culture at Ontario Hydro's Darlington Nuclear Station (4 x 932 Mwe CANDU units), and are beginning to show results. Programs designed for excellence in human performance have to provide clear simple structure, and draw people into alignment with the required behaviours. By making the structural elements and the alignment activities explicit an attempt can be made to ''design'' programs that will create and reinforce the required safety culture. The paper places the learning cycle at the heart of safety culture because the cycle aligns with the three attributes of safety culture. If an organization cannot learn from experience (i.e. change behaviours based on experience) it is doubtful whether it can build a strong safety culture. 2 refs

  16. Promotion of good safety culture at a Canadian HWR

    Energy Technology Data Exchange (ETDEWEB)

    Curle, B [Darlington NPP (Canada)

    1997-12-31

    People work at a nuclear plant within a structured environment. It is the programs, procedures and other ``tools`` that are used in the workplace that actually guide behaviours, and behaviours then guide performance. The safety culture in the workplace is ``the way we do things around here``. This culture is created by structures, behaviours and performance, and is characterized by three attributes: A questioning attitude; a rigorous and prudent approach; open 2-way communication. This paper discusses a model of safety culture which puts the operating experience or learning cycle program at the heart of the endeavor. This cycle also consists of three elements: Observation; reporting; learning. It is more of a theoretical paper than a report of success at this stage. However, the ideas presented are being used to design and implement a strong safety culture at Ontario Hydro`s Darlington Nuclear Station (4 x 932 Mwe CANDU units), and are beginning to show results. Programs designed for excellence in human performance have to provide clear simple structure, and draw people into alignment with the required behaviours. By making the structural elements and the alignment activities explicit an attempt can be made to ``design`` programs that will create and reinforce the required safety culture. The paper places the learning cycle at the heart of safety culture because the cycle aligns with the three attributes of safety culture. If an organization cannot learn from experience (i.e. change behaviours based on experience) it is doubtful whether it can build a strong safety culture. 2 refs.

  17. A Study on the Construct Validity of Safety Culture Oversight Model for Nuclear Power Operating Organization

    International Nuclear Information System (INIS)

    Jung, Su Jin; Choi, Young Sung; Oh, Jang Jin

    2015-01-01

    In Korea, the safety policy statement declared in 1994 by government stressed the importance of safety culture and licensees were encouraged to manage and conduct their self-assessments. A change in regulatory position about safety culture oversight was made after the event of SBO cover-up in Kori unit 1 and several subsequent falsification events. Since then KINS has been developing licensee's safety culture oversight system including conceptual framework of oversight, prime focus area for oversight, and specific details on regulatory expectations, all of which are based on defence-in-depth (DiD) safety enhancement approach. Development and gathering of performance data which is related to actual 'safety' of nuclear power plant are needed to identify the relationship between safety culture and safety performance. Authors consider this study as pilot which has a contribution on verifying the construct validity of the model and the effectiveness of survey based research. This is the first attempt that the validity of safety culture oversight model has been investigated with empirical data obtained from Korean nuclear power operating organization

  18. A Study on the Construct Validity of Safety Culture Oversight Model for Nuclear Power Operating Organization

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Su Jin; Choi, Young Sung; Oh, Jang Jin [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    In Korea, the safety policy statement declared in 1994 by government stressed the importance of safety culture and licensees were encouraged to manage and conduct their self-assessments. A change in regulatory position about safety culture oversight was made after the event of SBO cover-up in Kori unit 1 and several subsequent falsification events. Since then KINS has been developing licensee's safety culture oversight system including conceptual framework of oversight, prime focus area for oversight, and specific details on regulatory expectations, all of which are based on defence-in-depth (DiD) safety enhancement approach. Development and gathering of performance data which is related to actual 'safety' of nuclear power plant are needed to identify the relationship between safety culture and safety performance. Authors consider this study as pilot which has a contribution on verifying the construct validity of the model and the effectiveness of survey based research. This is the first attempt that the validity of safety culture oversight model has been investigated with empirical data obtained from Korean nuclear power operating organization.

  19. Implications of Self-Deception for Self-Reported Intrinsic and Extrinsic Motivational Dispositions and Actual Learning Performance: A Higher Order Structural Model

    Science.gov (United States)

    Hirschfeld, Robert R.; Thomas, Christopher H.; McNatt, D. Brian

    2008-01-01

    The authors explored implications of individuals' self-deception (a trait) for their self-reported intrinsic and extrinsic motivational dispositions and their actual learning performance. In doing so, a higher order structural model was developed and tested in which intrinsic and extrinsic motivational dispositions were underlying factors that…

  20. Occupational driver safety: conceptualising a leadership-based intervention to improve safe driving performance.

    Science.gov (United States)

    Newnam, Sharon; Lewis, Ioni; Watson, Barry

    2012-03-01

    Occupational driving crashes are the most common cause of death and injury in the workplace. The physical and psychological outcomes following injury are also very costly to organizations. Thus, safe driving poses a managerial challenge. Some research has attempted to address this issue through modifying discrete and often simple target behaviours (e.g., driver training programs). However, current intervention approaches in the occupational driving field generally consider the role of organizational factors in workplace safety. This study adopts the A-B-C framework to identify the contingencies associated with an effective exchange of safety information within the occupational driving context. Utilizing a sample of occupational drivers and their supervisors, this multi-level study examines the contingencies associated with the exchange of safety information within the supervisor-driver relationship. Safety values are identified as an antecedent of the safety information exchange, and the quality of the leader-member exchange relationship and safe driving performance is identified as the behavioural consequences. We also examine the function of role overload as a factor influencing the relationship between safety values and the safety information exchange. Hierarchical linear modelling found that role overload moderated the relationship between supervisors' perceptions of the value given to safety and the safety information exchange. A significant relationship was also found between the safety information exchange and the subsequent quality of the leader-member exchange relationship. Finally, the quality of the leader-member exchange relationship was found to be significantly associated with safe driving performance. Theoretical and practical implications of these results are discussed. Copyright © 2011 Elsevier Ltd. All rights reserved.

  1. Investigation of road network features and safety performance.

    Science.gov (United States)

    Wang, Xuesong; Wu, Xingwei; Abdel-Aty, Mohamed; Tremont, Paul J

    2013-07-01

    The analysis of road network designs can provide useful information to transportation planners as they seek to improve the safety of road networks. The objectives of this study were to compare and define the effective road network indices and to analyze the relationship between road network structure and traffic safety at the level of the Traffic Analysis Zone (TAZ). One problem in comparing different road networks is establishing criteria that can be used to scale networks in terms of their structures. Based on data from Orange and Hillsborough Counties in Florida, road network structural properties within TAZs were scaled using 3 indices: Closeness Centrality, Betweenness Centrality, and Meshedness Coefficient. The Meshedness Coefficient performed best in capturing the structural features of the road network. Bayesian Conditional Autoregressive (CAR) models were developed to assess the safety of various network configurations as measured by total crashes, crashes on state roads, and crashes on local roads. The models' results showed that crash frequencies on local roads were closely related to factors within the TAZs (e.g., zonal network structure, TAZ population), while crash frequencies on state roads were closely related to the road and traffic features of state roads. For the safety effects of different networks, the Grid type was associated with the highest frequency of crashes, followed by the Mixed type, the Loops & Lollipops type, and the Sparse type. This study shows that it is possible to develop a quantitative scale for structural properties of a road network, and to use that scale to calculate the relationships between network structural properties and safety. Copyright © 2013 Elsevier Ltd. All rights reserved.

  2. Gamma-ray shielding design and performance test of WASTEF

    International Nuclear Information System (INIS)

    Matsumoto, Seiichiro; Aoyama, Saburo; Tashiro, Shingo; Nagai, Shiro

    1984-06-01

    The Waste Safety Testing Facility (WASTEF) was planned in 1978 to test the safety performance of HLW vitrified forms under the simulated conditions of long term storage and disposal, and completed in August 1981. The designed feature of the facility is to treat the vitrified forms contain actual high-level wastes of 5 x 10 4 Ci in maximum with 5 units of concrete shilded hot cells (3 units : Bate-Gamma cells, 2 units : Alpha-Gamma cells) and one units of Alpha-Gamma lead shielded cell, and to store radioactivity of 10 6 Ci in maximum. The safety performance of this facility is fundamentally maintained with confinement of radioactivity and shielding of the radiation. This report describes the method of gamma-ray shielding design, evaluation of the shielding test performed by using sealded gamma-ray sources(Co-60). (author)

  3. The effect of Health, Safety and Environment Management System (HSE-MS on the improvement of safety performance indices in Urea and Ammonia Kermanshah Petrochemical Company

    Directory of Open Access Journals (Sweden)

    M. S. Poursoleiman

    2015-09-01

    Full Text Available Introduction: Work-related accidents may cause damage to people, environment and lead to waste of time and money. Health, Safety and Environment Management System has been developed in order to reduce accidents. This study aimed to investigate the effect of implementation of this system on reduction of the accidents and its consequences and also on the safety performance indices in Kermanshah Petrochemical Company. Material and Method: In this study, records of accidents were collected by OSHA incident report form 301 over 4 years. Following, the mean annual accidents and its consequences and safety performance indices were calculated and reported. Then, using statistical analysis, the impacts of two years implementation of this system on the accidents and its consequences and safety performance indices were evaluated. Result: The results showed that the implementation of HSE system was significantly correlated with Frequency Severity Indicator, Accident Severity Rate, lost days, minor accidents and total incidents (P-value 0.05. Conclusion: The implementation of Health, Safety and the Environment Management System caused a reduction in accidents and its consequences and most of the safety performance indices in the entire process cycle of Kermanshah Petrochemical Company. Overall, safety condition has been improved considerably.

  4. Applying a realistic evaluation model to occupational safety interventions

    DEFF Research Database (Denmark)

    Pedersen, Louise Møller

    2018-01-01

    Background: Recent literature characterizes occupational safety interventions as complex social activities, applied in complex and dynamic social systems. Hence, the actual outcomes of an intervention will vary, depending on the intervention, the implementation process, context, personal characte......Background: Recent literature characterizes occupational safety interventions as complex social activities, applied in complex and dynamic social systems. Hence, the actual outcomes of an intervention will vary, depending on the intervention, the implementation process, context, personal...... and qualitative methods. This revised model has, however, not been applied in a real life context. Method: The model is applied in a controlled, four-component, integrated behaviour-based and safety culture-based safety intervention study (2008-2010) in a medium-sized wood manufacturing company. The interventions...... involve the company’s safety committee, safety manager, safety groups and 130 workers. Results: The model provides a framework for more valid evidence of what works within injury prevention. Affective commitment and role behaviour among key actors are identified as crucial for the implementation...

  5. Safety and performance indicators for repositories in salt and clay formations

    International Nuclear Information System (INIS)

    Wolf, Jens; Ruebel, Andre; Noseck, Ulrich; Becker, Dirk

    2008-07-01

    The GRS (Gesellschaft fuer Reaktorsicherheit) study aims to the identification of suitable indicators for repositories in salt and clay formation. It is not intended to compare the two formations with respect to the safe disposal of radioactive waste. A first set of safety and performance indicators for both host rocks has been derived on the basis of results of the SPIN project. Reference values for the safety indicators have been determined. The suitability of the indicators and their significance for different time frames Is demonstrated by means of deterministic model calculations and external parameter variations of previous studies. The safety indicators considered in the report are the effective dose rate (Sv/a), the radiotoxicity concentration in the biosphere water (Sv/m 3 ) and the radiotoxicity flux from the geosphere (overlying rock) (Sv/a). The performance indicators considered in the study are the radiotoxicity inventory in different compartments (S), radiotoxicity fluxes from compartments and the integrated radiotoxicity fluxes from compartments (Sv).

  6. Motivators to participation in actual HIV vaccine trials.

    Science.gov (United States)

    Dhalla, Shayesta; Poole, Gary

    2014-02-01

    An examination of actual HIV vaccine trials can contribute to an understanding of motivators for participation in these studies. Analysis of these motivators reveals that they can be categorized as social and personal benefits. Social benefits are generally altruistic, whereas personal benefits are psychological, physical, and financial. In this systematic review, the authors performed a literature search for actual preventive HIV vaccine trials reporting motivators to participation. Of studies conducted in the Organization for Economic Co-operation and Development (OECD) countries, the authors retrieved 12 studies reporting on social benefits and seven reporting on personal benefits. From the non-OECD countries, nine studies reported on social benefits and eight studies on personal benefits. Social benefits were most frequently described on macroscopic, altruistic levels. Personal benefits were most frequently psychological in nature. Rates of participation were compared between the OECD and the non-OECD countries. Knowledge of actual motivators in specific countries and regions can help target recruitment in various types of actual HIV vaccine trials.

  7. Operational safety performance indicator system at the Dukovany Nuclear Power Plant - Experience with indicator aggregation

    International Nuclear Information System (INIS)

    Mandula, J.

    2001-01-01

    The operational safety performance indicators serve as an important tool of performance monitoring and management at the Dukovany NPP. A software-supported system has been developed, which has included: data collection, central data storage, graphic output production and periodical report generation. Analyses of performance indicator trends together with evaluation in respect of annually updated target values and acceptance criteria are used for operational safety reviews forming an integral part of continual self-assessment process. This contribution has been focused on experience obtained during development of the operational safety assessment model using indicator aggregation. It summarises problems that had to be paid specific attention in the development process. Thanks to their solution, the model has become a synoptic monitor and a useful tool for operational safety assessment. (author)

  8. Barrier and system performances within a safety case: their functioning and evolution with time

    International Nuclear Information System (INIS)

    Hedin, A.; Voinis, S.; Fillion, E.; Keller, S.; Lalieux, Ph.; Nachmilner, L.; Nys, V.; Rodriguez, J.; Sevougian, D.; Wollrath, J.

    2002-01-01

    The following six questions were used as the basis for the discussions in a Working Group: - What is the role of each barrier as a function of time or in the different time frames? What is its contribution to the overall system performance or safety as a function of time? - Which are the main uncertainties on the performance of barriers in the timescales? To what extent should we enhance the robustness of barriers because of the uncertainties of some component behaviour with time? - What is the requested or required performance versus the expected realistic or conservative behaviour with time? How are these safety margins used as arguments in a safety case? - What is the issue associated with the geosphere stability for different geological systems? - How are barriers and system performances, as a function of time, evaluated (presented and communicated) in a safety case? - What kind of measures are used for siting, designing and optimising robust barriers corresponding to situations that can vary with time? Are human actions considered to be relevant? (authors)

  9. Numerical indicators of nuclear power plant safety performance

    International Nuclear Information System (INIS)

    1991-04-01

    The workshop was attended by representatives from twenty-two Member States operating nuclear power plants (NPP). The current status of the development and use of numerical indicators of NPP safety performance was presented. A consensus on the benefits of use of numerical indicators was reached. The Technical Committee Meeting reviewed the progress in the development and use of performance indicators and identified them as the most appropriate ones for international use. The purpose of this document is to summarize the discussions held and conclusions reached in both meetings. Lists of participants and all the papers of both meetings are presented

  10. Westinghouse Hanford Company health and safety performance report

    International Nuclear Information System (INIS)

    Rogers, L.

    1996-01-01

    Topping the list of WHC Safety recognition during this reporting period is a commendation received from the National Safety Council (NSC). The NSC bestowed their Award of Honor upon WHC for significant reduction of incidence rates during CY 1995. The award is based upon a reduction of 48 % or greater in cases involving days away from work, a 30 % or greater reduction in the number of days away, and a 15% or greater reduction in the total number of occupational injuries and illnesses. (page 2-1). A DOE-HQ review team representing the Office of Envirorunent, Safety and Health (EH), visited the Hanford Site during several weeks of the quarter. Ile 40-member Safety Management Evaluation Team (SMET) assessed WHC in the areas of management responsibility, comprehensive requirements, and competence commensurate with responsibility. As part of their new approach to oversight, they focused on the existence of management systems and programs (comparable approach to VPP). Plant/project areas selected for review within WHC were PFP, B Plant/WESF, Tank Farms, and K-Basins (page 2-2). Effective safety meetings, prejob safety meetings, etc., are a cornerstone of any successful safety program. In an effort to improve the reporting of safety meetings, the Safety/Security Meeting Report form was revised. It now provides a mechanism for recording and tracking safety issues (page 2-4). WHC has experienced an increase in the occupational injury and illness incidence rates during the first quarter of CY 1996. Trends show this increase can be partially attributed to inattention to workplace activities due 0999to the uncertainty Hanford employees currently face with recent reduction of force, reorganization, and reengineering efforts (page 2-7). The cumulative CY 1995 lost/restricted workday case incidence rate for the first quarter of CY 1996 (1.28) is 25% below the DOE CY 1991-93 average (1.70). However, the incidence rate increased 24% from the CY 1995 rate of 1.03 (page 2-8). The

  11. Westinghouse Hanford Company health and safety performance report

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, L.

    1996-05-15

    Topping the list of WHC Safety recognition during this reporting period is a commendation received from the National Safety Council (NSC). The NSC bestowed their Award of Honor upon WHC for significant reduction of incidence rates during CY 1995. The award is based upon a reduction of 48 % or greater in cases involving days away from work, a 30 % or greater reduction in the number of days away, and a 15% or greater reduction in the total number of occupational injuries and illnesses. (page 2-1). A DOE-HQ review team representing the Office of Envirorunent, Safety and Health (EH), visited the Hanford Site during several weeks of the quarter. Ile 40-member Safety Management Evaluation Team (SMET) assessed WHC in the areas of management responsibility, comprehensive requirements, and competence commensurate with responsibility. As part of their new approach to oversight, they focused on the existence of management systems and programs (comparable approach to VPP). Plant/project areas selected for review within WHC were PFP, B Plant/WESF, Tank Farms, and K-Basins (page 2-2). Effective safety meetings, prejob safety meetings, etc., are a cornerstone of any successful safety program. In an effort to improve the reporting of safety meetings, the Safety/Security Meeting Report form was revised. It now provides a mechanism for recording and tracking safety issues (page 2-4). WHC has experienced an increase in the occupational injury and illness incidence rates during the first quarter of CY 1996. Trends show this increase can be partially attributed to inattention to workplace activities due 0999to the uncertainty Hanford employees currently face with recent reduction of force, reorganization, and reengineering efforts (page 2-7). The cumulative CY 1995 lost/restricted workday case incidence rate for the first quarter of CY 1996 (1.28) is 25% below the DOE CY 1991-93 average (1.70). However, the incidence rate increased 24% from the CY 1995 rate of 1.03 (page 2-8). The

  12. Proceedings of the specialist meeting on safety performance indicators

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-05-28

    In 1998, the OECD/NEA committee on Nuclear Regulatory Activities (CNRA) initiated an activity with the objective of advancing the discussion on how to enhance and measure regulatory effectiveness in relation to nuclear installations. One of the outcome of this activity was to establish a Task group to develop internal (direct) performance indicators which would be used to monitor regulatory efficiency. On the initiative of the NEA/CSNI Working Group on Operating Experience the Spanish CSN hosted a workshop (Madrid, 2000) to review the state of the art on Safety Performance Indicators. This workshop, which was co-sponsored by the IAEA and WANO was attended by 73 participants from 19 countries, representing the industry, regulators, service companies as well as international organisations. The conclusions were: 1. there is considerable development effort on performance indicators in many countries; 2. utilities continue to rely on the WANO Performance indicators system which consists of indicators in 8 key areas and receives data from virtually all commercial NPP's in the world; 3. Regulators do not have a common set of performance indicators. This document gathers the 25 presentations given during this workshop. After this workshop, a joint CNRA/CSNI task group was launched in December 2000 to exchange information and develop external (indirect) indicators to measure regulatory effectiveness, i.e. impact on licensee's safety performance. These external indicators are, in other words, the traditional plant performance indicators (PI's). The task force consisted of regulators, organisations which have a performance indicators system in operation or under testing. The task force met in Paris on February 19-20, 2001 and the work performed by the group is summarized in a report (NEA-CSNI-R--2001-11) attached in appendix to these proceedings.

  13. Proceedings of the specialist meeting on safety performance indicators

    International Nuclear Information System (INIS)

    2002-01-01

    In 1998, the OECD/NEA committee on Nuclear Regulatory Activities (CNRA) initiated an activity with the objective of advancing the discussion on how to enhance and measure regulatory effectiveness in relation to nuclear installations. One of the outcome of this activity was to establish a Task group to develop internal (direct) performance indicators which would be used to monitor regulatory efficiency. On the initiative of the NEA/CSNI Working Group on Operating Experience the Spanish CSN hosted a workshop (Madrid, 2000) to review the state of the art on Safety Performance Indicators. This workshop, which was co-sponsored by the IAEA and WANO was attended by 73 participants from 19 countries, representing the industry, regulators, service companies as well as international organisations. The conclusions were: 1. there is considerable development effort on performance indicators in many countries; 2. utilities continue to rely on the WANO Performance indicators system which consists of indicators in 8 key areas and receives data from virtually all commercial NPP's in the world; 3. Regulators do not have a common set of performance indicators. This document gathers the 25 presentations given during this workshop. After this workshop, a joint CNRA/CSNI task group was launched in December 2000 to exchange information and develop external (indirect) indicators to measure regulatory effectiveness, i.e. impact on licensee's safety performance. These external indicators are, in other words, the traditional plant performance indicators (PI's). The task force consisted of regulators, organisations which have a performance indicators system in operation or under testing. The task force met in Paris on February 19-20, 2001 and the work performed by the group is summarized in a report (NEA-CSNI-R--2001-11) attached in appendix to these proceedings

  14. The relationship between UT reported size and actual size of the defects in rotor forgings

    International Nuclear Information System (INIS)

    Seong, Un Hak; Kim, Jeong Tae; Park, Yun Sik

    2003-01-01

    In order to evaluate the reliability of rotor forgings, it is very important to know the actual size of the defects in the rotor forgings. The determination of the defect size requires the accurate non-destructive measurement. However, there may be some differences between the reported size with the ultrasonic non-destructive testing method and the actual size of defects. These differences may be a severe cause of errors in evaluation of rotor forgings. So, the calculated size with 'Master Curve' considering safety factor, which is usually larger than the reported size, has been used in evaluation of rotor forgings. The relation between the EFBH (Equivalent Flat Bottom Hole) size measured by non-destructive method and the actual size by destructive method in many rotors manufactured at Doosan was investigated. In this investigation 'Master Curve' compensating the differences between UT reported size and actual size of defects in our rotor forgings was obtainable. The applicability of this 'Master Curve' as a way of calculating the actual defect size was also investigated. For the evaluation of rotor forgings, it is expected that this 'Master Curve' may be used to determine the accurate actual size of defects.

  15. The relationship between UT reported size and actual size of the defects in rotor forgings

    International Nuclear Information System (INIS)

    Seong, Un Hak; Kim, Jeong Tae; Park, Yun Sik

    2003-01-01

    In order to evaluate the reliability of rotor forgings, it is very important to know the actual size of the defects in the rotor forgings. The determination of the defect size requires the accurate non-destructive measurement. However, there may be some difference between the reported size with ultrasonic non-destructive testing method and the actual size of defects. These differences may be a severe cause of errors in evaluation of rotor forgings. So, the calculated size with 'Master Curve' considering safety factor, which is usually larger than the reported size, has been used in evaluation of rotor forgings. The relation between the EFBH (Equivalent Flat Bottom Hole) size measured by non-destructive method and the actual size by destructive method in many rotors manufactured at Doosan was investigated. In this investigation, 'Master Curve' compensating the differences between UT reported size and actual size of defects in our rotor forgings was obtainable. The applicability of this 'Master Curve' as a way of calculating the actual defect size was also investigated. For the evaluation of rotor forgings, it is expected that this 'Master Curve' may be used to determine the accurate actual size of defects.

  16. Dukovany nuclear power plant safety

    International Nuclear Information System (INIS)

    1999-01-01

    Presentation covers recommended safety issues for the Dukovany NPP which have been solved with satisfactory conclusions. Safety issues concerned include: radiation safety; nuclear safety; security; emergency preparedness; health protection at work; fire protection; environmental protection; chemical safety; technical safety. Quality assurance programs at all stages on NPP life time is described. Report includes description of NPP staff training provision, training simulator, emergency operating procedures, emergency preparedness, Year 2000 problem, inspections and life time management. Description of Dukovany Plant Safety Analysis Projects including integrity of the equipment, modernisation, equipment innovation and safety upgrading program show that this approach corresponds to the actual practice applied in EU countries, and fulfilment of current IAEA requirements for safety enhancement of the WWER 440/213 units in the course of MORAWA Equipment Upgrading program

  17. A dose-ranging study of the effects of mequitazine on actual driving, memory and psychomotor performance as compared to dexchlorpheniramine, cetirizine and placebo.

    Science.gov (United States)

    Theunissen, E L; Vermeeren, A; van Oers, A C M; van Maris, I; Ramaekers, J G

    2004-02-01

    Mequitazine is a so-called 'non-sedative' second-generation antihistamine even though it has never been firmly established that this drug's sedative potential actually differs from that of the 'sedative' first-generation antihistamines. The present study compares the sedative effects of three doses of mequitazine on actual driving, psychomotor performance and memory with those of a first- and a second-generation antihistamine. Eighteen healthy volunteers received on separate days a single dose of 5, 10 and 15 mg mequitazine, 10 mg cetirizine, 6 mg dexchlorpheniramine and placebo. Drug effects were assessed using two actual driving tests (highway-driving test and car-following test), cognitive and psychometric tests (tracking, divided attention, memory, reasoning and critical flicker fusion), pupil size and questionnaires. Highway-driving data revealed an overall effect of Treatment on the standard deviation of lateral position (SDLP). Dexchlorpheniramine impaired driving performance as indicated by a significant rise in SDLP. Mequitazine significantly increased SDLP in a dose-related manner, but the separate dose effects failed to reach statistical significance. Divided attention performance was also affected by Treatment. Reaction time (RT) during mequitazine treatments increased in a dose-related manner and significantly differed from placebo at the highest dose. Subjects reported to be less alert after treatment with dexchlorpheniramine. Cetirizine did not affect performance in any of the tasks. It was concluded that mequitazine is mildly sedating. The effects of mequitazine are comparable to those of other second-generation antihistamines, in that it causes mild driving impairment, particularly at higher doses.

  18. An aspect-oriented approach for designing safety-critical systems

    Science.gov (United States)

    Petrov, Z.; Zaykov, P. G.; Cardoso, J. P.; Coutinho, J. G. F.; Diniz, P. C.; Luk, W.

    The development of avionics systems is typically a tedious and cumbersome process. In addition to the required functions, developers must consider various and often conflicting non-functional requirements such as safety, performance, and energy efficiency. Certainly, an integrated approach with a seamless design flow that is capable of requirements modelling and supporting refinement down to an actual implementation in a traceable way, may lead to a significant acceleration of development cycles. This paper presents an aspect-oriented approach supported by a tool chain that deals with functional and non-functional requirements in an integrated manner. It also discusses how the approach can be applied to development of safety-critical systems and provides experimental results.

  19. Site Safety Plan for Lawrence Livermore National Laboratory CERCLA investigations

    Energy Technology Data Exchange (ETDEWEB)

    Bainer, R.; Duarte, J.

    1993-07-01

    The safety policy of LLNL is to take every reasonable precaution in the performance of work to protect the environment and the health and safety of employees and the public, and to prevent property damage. With respect to hazardous agents, this protection is provided by limiting human exposures, releases to the environment, and contamination of property to levels that are as low as reasonably achievable (ALARA). It is the intent of this Plan to supply the broad outline for completing environmental investigations within ALARA guidelines. It may not be possible to determine actual working conditions in advance of the work; therefore, planning must allow the opportunity to provide a range of protection based upon actual working conditions. Requirements will be the least restrictive possible for a given set of circumstances, such that work can be completed in an efficient and timely fashion. Due to the relatively large size of the LLNL Site and the different types of activities underway, site-specific Operational Safety Procedures (OSPs) will be prepared to supplement activities not covered by this Plan. These site-specific OSPs provide the detailed information for each specific activity and act as an addendum to this Plan, which provides the general plan for LLNL Main Site operation.

  20. Application of CFD Codes in Nuclear Reactor Safety Analysis

    Directory of Open Access Journals (Sweden)

    T. Höhne

    2010-01-01

    Full Text Available Computational Fluid Dynamics (CFD is increasingly being used in nuclear reactor safety (NRS analyses as a tool that enables safety relevant phenomena occurring in the reactor coolant system to be described in more detail. Numerical investigations on single phase coolant mixing in Pressurised Water Reactors (PWR have been performed at the FZD for almost a decade. The work is aimed at describing the mixing phenomena relevant for both safety analysis, particularly in steam line break and boron dilution scenarios, and mixing phenomena of interest for economical operation and the structural integrity. For the experimental investigation of horizontal two phase flows, different non pressurized channels and the TOPFLOW Hot Leg model in a pressure chamber was build and simulated with ANSYS CFX. In a common project between the University of Applied Sciences Zittau/Görlitz and FZD the behaviour of insulation material released by a LOCA released into the containment and might compromise the long term emergency cooling systems is investigated. Moreover, the actual capability of CFD is shown to contribute to fuel rod bundle design with a good CHF performance.

  1. Who is Self-Actualized?

    Science.gov (United States)

    Roweton, William E.

    1981-01-01

    In an attempt to clarify Maslow's concept of self-actualization as it relates to human motivation, a class of educational psychology students wrote essays describing a self-actualized person and then attempted to decide whether public schools contribute to the production of self-actualized persons. Two-thirds of the students decided that schools…

  2. Determinants of safety outcomes and performance: A systematic literature review of research in four high-risk industries.

    Science.gov (United States)

    Cornelissen, Pieter A; Van Hoof, Joris J; De Jong, Menno D T

    2017-09-01

    In spite of increasing governmental and organizational efforts, organizations still struggle to improve the safety of their employees as evidenced by the yearly 2.3 million work-related deaths worldwide. Occupational safety research is scattered and inaccessible, especially for practitioners. Through systematically reviewing the safety literature, this study aims to provide a comprehensive overview of behavioral and circumstantial factors that endanger or support employee safety. A broad search on occupational safety literature using four online bibliographical databases yielded 27.527 articles. Through a systematic reviewing process 176 online articles were identified that met the inclusion criteria (e.g., original peer-reviewed research; conducted in selected high-risk industries; published between 1980-2016). Variables and the nature of their interrelationships (i.e., positive, negative, or nonsignificant) were extracted, and then grouped and classified through a process of bottom-up coding. The results indicate that safety outcomes and performance prevail as dependent research areas, dependent on variables related to management & colleagues, work(place) characteristics & circumstances, employee demographics, climate & culture, and external factors. Consensus was found for five variables related to safety outcomes and seven variables related to performance, while there is debate about 31 other relationships. Last, 21 variables related to safety outcomes and performance appear understudied. The majority of safety research has focused on addressing negative safety outcomes and performance through variables related to others within the organization, the work(place) itself, employee demographics, and-to a lesser extent-climate & culture and external factors. This systematic literature review provides both scientists and safety practitioners an overview of the (under)studied behavioral and circumstantial factors related to occupational safety behavior. Scientists

  3. Road safety performance indicators for the interurban road network.

    Science.gov (United States)

    Yannis, George; Weijermars, Wendy; Gitelman, Victoria; Vis, Martijn; Chaziris, Antonis; Papadimitriou, Eleonora; Azevedo, Carlos Lima

    2013-11-01

    Various road safety performance indicators (SPIs) have been proposed for different road safety research areas, mainly as regards driver behaviour (e.g. seat belt use, alcohol, drugs, etc.) and vehicles (e.g. passive safety); however, no SPIs for the road network and design have been developed. The objective of this research is the development of an SPI for the road network, to be used as a benchmark for cross-region comparisons. The developed SPI essentially makes a comparison of the existing road network to the theoretically required one, defined as one which meets some minimum requirements with respect to road safety. This paper presents a theoretical concept for the determination of this SPI as well as a translation of this theory into a practical method. Also, the method is applied in a number of pilot countries namely the Netherlands, Portugal, Greece and Israel. The results show that the SPI could be efficiently calculated in all countries, despite some differences in the data sources. In general, the calculated overall SPI scores were realistic and ranged from 81 to 94%, with the exception of Greece where the SPI was relatively lower (67%). However, the SPI should be considered as a first attempt to determine the safety level of the road network. The proposed method has some limitations and could be further improved. The paper presents directions for further research to further develop the SPI. Copyright © 2012 Elsevier Ltd. All rights reserved.

  4. Performance Evaluation and Analysis of Rural Drinking Water Safety Project——A Case Study in Jiangsu, China

    Science.gov (United States)

    Du, Xiaorong

    2017-04-01

    Water is the basic condition for human survival and development. As China is the most populous country, rural drinking water safety problems are most conspicuous. Therefore, the Chinese government keeps increasing investment and has built a large number of rural drinking water safety projects. Scientific evaluation of project performance is of great significance to promote the sustainable operation of the project and the sustainable development of rural economy. Previous studies mainly focus on the economic benefits of the project, while ignoring the fact that the rural drinking water safety project is quasi-public goods, which has economic, social and ecological benefits. This paper establishes a comprehensive evaluation model for rural drinking water safety performance, which adapts the rules of "5E" (economy, efficiency, effectiveness, equity and environment) as the value orientation, and selects a rural drinking water safety project as object in case study at K District, which is in the north of Jiangsu Province, China. The results shows: 1) the comprehensive performance of K project is in good condition; 2) The performance of every part shows that the scores of criteria "efficiency", "environment" and "effect" are higher than the mean performance, while the "economy" is slightly lower than the mean and the "equity" is the lowest. 3) The performance of indicator layer shows that: the planned completion rate of project, the reduction rate of project cost and the penetration rate of water-use population are significantly lower than other indicators. Based on the achievements of previous studies and the characteristics of rural drinking water safety project, this study integrates the evaluation dimensions of equity and environment, which can contribute to a more comprehensive and systematic assessment of project performance and provide empirical data for performance evaluation and management of rural drinking water safety project. Key Words: Rural drinking water

  5. Defining safety culture and the nexus between safety goals and safety culture. 1. An Investigation Study on Practical Points of Safety Management

    International Nuclear Information System (INIS)

    Hasegawa, Naoko; Takano, Kenichi; Hirose, Ayako

    2001-01-01

    among those of existing questionnaires about safety culture, organizational climate, and individual safety consciousness. From the results of investigations, it was supposed that the establishment of a safety management system to which the whole organization is committed and that has top-down and bottom-up cycles is necessary to enhance organization safety. For example, it was clarified that employee safety consciousness is relevant to 'the action of safety management section' and to two kinds of organization climate, i.e., 'good human relationship' and 'frequent discussion on safety'. As for worker motivation for safety, it was clarified that commitment to safety activities was directly influenced by 'safety activities adhering to actual work sites', 'advance check', and 'frequent discussion on safety' as a result of correlation analysis among traits of safety activity, attitude during daily work, and organizational climate (Fig. 1). In addition, it was also supposed that the commitment was influenced by 'good human relationship', 'pride in work', and 'communication between head office and work sites' indirectly according to the result of the same analysis. Thus, it is supposed that ideas to make safety activities adhere to actual work sites and good human relationships are necessary for organization safety as well as for the establishment of the safety management system. The state of the organization and work sites before the safety system and activities are enforced must also be assessed. According to the results, the construction, chemical, and manufacturing industries differed in types of safety systems and activities conducted because the system types and activities to be conducted depended on the type of work or work site. Hence, to diagnose an organization and to provide an appropriate safety system and activities that reflect the diagnosis are important to enforce safety culture from the viewpoint of usability and interface of the safety management system

  6. Guidance on the implementation of a risk based safety performance monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Sewell, R.T.; Kuritzky, A.S.; Khatib-Rahbar, M.

    1997-05-01

    The principal objective of the present study is to review and evaluate existing Performance Indicator (PI) monitoring programs, and to develop and demonstrate an overall PSA-based methodology and framework for the monitoring and use of risk-based PIs and SIs (Safety Indicator), that would enable: Identification of trends and patterns in safety performance at a specific plant and a population of plants; Assessment of the significance of the trends and patterns; Identification of precursors of accident sequences and safety reductions; Identification of the most critical functional areas of concern, especially as they relate to a defense-in-depth safety philosophy; Comparison of safety performance trends at a plant with those at comparable plants; Incorporation of the PIs and SIs into a risk- and performance-based decision process. To support the overall project objective, it is important that information needs and data collection procedures are clearly outlined. Of key significance in this regard is the premise that a performance monitoring system should not be burdened by an excessive number of low-level PIs that may have only a peripheral relationship to safety. Other supporting objectives of the study include: To identify and discuss other issues pertaining to the practical implementation of a safety performance monitoring system (outlining the databases and algorithms needed); and to demonstrate implementation of the preliminary guidance for monitoring and use of the selected set of PIs and SIs, within the proposed framework, via application to the operating history of a NPP having a PSA and readily available event data

  7. Does lean management improve patient safety culture? An extensive evaluation of safety culture in a radiotherapy institute.

    Science.gov (United States)

    Simons, Pascale A M; Houben, Ruud; Vlayen, Annemie; Hellings, Johan; Pijls-Johannesma, Madelon; Marneffe, Wim; Vandijck, Dominique

    2015-02-01

    The importance of a safety culture to maximize safety is no longer questioned. However, achieving sustainable culture improvements are less evident. Evidence is growing for a multifaceted approach, where multiple safety interventions are combined. Lean management is such an integral approach to improve safety, quality and efficiency and therefore, could be expected to improve the safety culture. This paper presents the effects of lean management activities on the patient safety culture in a radiotherapy institute. Patient safety culture was evaluated over a three year period using triangulation of methodologies. Two surveys were distributed three times, workshops were performed twice, data from an incident reporting system (IRS) was monitored and results were explored using structured interviews with professionals. Averages, chi-square, logistical and multi-level regression were used for analysis. The workshops showed no changes in safety culture, whereas the surveys showed improvements on six out of twelve dimensions of safety climate. The intention to report incidents not reaching patient-level decreased in accordance with the decreasing number of reports in the IRS. However, the intention to take action in order to prevent future incidents improved (factorial survey presented β: 1.19 with p: 0.01). Due to increased problem solving and improvements in equipment, the number of incidents decreased. Although the intention to report incidents not reaching patient-level decreased, employees experienced sustained safety awareness and an increased intention to structurally improve. The patient safety culture improved due to the lean activities combined with an organizational restructure, and actual patient safety outcomes might have improved as well. Copyright © 2014 Elsevier Ltd. All rights reserved.

  8. Benchmarking road safety performance by grouping local territories : a study in The Netherlands.

    NARCIS (Netherlands)

    Aarts, L.T. & Houwing, S.

    2015-01-01

    The method of benchmarking provides an opportunity to learn from better performing territories to improve the effectiveness and efficiency of activities in a particular field of interest. Such a field of interest could be road safety. Road safety benchmarking can include several indicators, ranging

  9. Contractors’ Attitude towards Enhancing Safety Performance: Case Study on Construction Firms in Penang

    Directory of Open Access Journals (Sweden)

    Ulang N. Md

    2014-01-01

    Full Text Available A qualitative study was conducted to investigate the contractors’ attitude towards enhancing the safety performance in construction site. Despite the fact that there are many safety initiatives established by the government, the rates of accidents are still in a critically high condition. Thus the purpose of this research is to study the contractors’ attitude towards enhancing the implementation of safety management system in construction site in order to increase the safety awareness of construction practitioners in construction site and improve the safety condition of construction sites. This study is conducted through oral interviews with the construction practitioners, and visual inspection of construction sites. The attitudes of contractors are evaluated from 3 aspects: Contractors’ efforts in implement and enforce the safety rules, Contractors efforts in overcoming the rate of accidents, and Reasons given by the contractors for not implement safety law.

  10. Identifying the most significant indicators of the total road safety performance index.

    Science.gov (United States)

    Tešić, Milan; Hermans, Elke; Lipovac, Krsto; Pešić, Dalibor

    2018-04-01

    The review of the national and international literature dealing with the assessment of the road safety level has shown great efforts of the authors who tried to define the methodology for calculating the composite road safety index on a territory (region, state, etc.). The procedure for obtaining a road safety composite index of an area has been largely harmonized. The question that has not been fully resolved yet concerns the selection of indicators. There is a wide range of road safety indicators used to show a road safety situation on a territory. Road safety performance index (RSPI) obtained on the basis of a larger number of safety performance indicators (SPIs) enable decision makers to more precisely define the earlier goal- oriented actions. However, recording a broader comprehensive set of SPIs helps identify the strengths and weaknesses of a country's road safety system. Providing high quality national and international databases that would include comparable SPIs seems to be difficult since a larger number of countries dispose of a small number of identical indicators available for use. Therefore, there is a need for calculating a road safety performance index with a limited number of indicators (RSPI ln n ) which will provide a comparison of a sufficient quality, of as many countries as possible. The application of the Data Envelopment Analysis (DEA) method and correlative analysis has helped to check if the RSPI ln n is likely to be of sufficient quality. A strong correlation between the RSPI ln n and the RSPI has been identified using the proposed methodology. Based on this, the most contributing indicators and methodologies for gradual monitoring of SPIs, have been defined for each country analyzed. The indicator monitoring phases in the analyzed countries have been defined in the following way: Phase 1- the indicators relating to alcohol, speed and protective systems; Phase 2- the indicators relating to roads and Phase 3- the indicators relating to

  11. Risk-informed, performance-based safety-security interface

    International Nuclear Information System (INIS)

    Mrowca, B.; Eltawila, F.

    2012-01-01

    Safety-security interface is a term that is used as part of the commercial nuclear power security framework to promote coordination of the many potentially adverse interactions between plant security and plant safety. Its object is to prevent the compromise of either. It is also used to describe the concept of building security into a plant's design similar to the long standing practices used for safety therefore reducing the complexity of the operational security while maintaining or enhancing overall security. With this in mind, the concept of safety-security interface, when fully implemented, can influence a plant's design, operation and maintenance. It brings the approach use for plant security to one that is similar to that used for safety. Also, as with safety, the application of risk-informed techniques to fully implement and integrate safety and security is important. Just as designers and operators have applied these techniques to enhance and focus safety, these same techniques can be applied to security to not only enhance and focus the security but also to aid in the implementation of effective techniques to address the safety-security interfaces. Implementing this safety-security concept early within the design process can prevent or reduce security vulnerabilities through low cost solutions that often become difficult and expensive to retrofit later in the design and/or post construction period. These security considerations address many of the same issues as safety in ensuring that the response of equipment and plant personnel are adequate. That is, both safety and security are focused on reaching safe shutdown and preventing radiological release. However, the initiation of challenges and the progression of actions in response these challenges and even the definitions of safe shutdown can be considerably different. This paper explores the techniques and limitations that are employed to fully implement a risk-informed, safety-security interface

  12. Performance and safety design of the advanced liquid metal reactor

    International Nuclear Information System (INIS)

    Berglund, R.C.; Magee, P.M.; Boardman, C.E.; Gyorey, G.L.

    1991-01-01

    The Advanced Liquid Metal Reactor (ALMR) program led by General Electric is developing, under U.S. Department of Energy sponsorship, a conceptual design for an advanced sodium-cooled liquid metal reactor plant. This design is intended to improve the already excellent level of plant safety achieved by the nuclear power industry while at the same time providing significant reductions in plant construction and operating costs. In this paper, the plant design and performance are reviewed, with emphasis on the ALMR's unique passive design safety features and its capability to utilize as fuel the actinides in LWR spent fuel

  13. The Tiotropium Safety and Performance in Respimat® (TIOSPIR®) Trial

    DEFF Research Database (Denmark)

    Anzueto, Antonio; Wise, Robert; Calverley, Peter

    2015-01-01

    ). The rate of FEV1 decline in GOLD I + II patients was greater than in GOLD III + IV patients (46 vs. 23 mL/year); as well as in current versus ex-smokers, in patients receiving combination therapies at baseline versus not, and in those experiencing an exacerbation during the study versus not. CONCLUSIONS......BACKGROUND: Tiotropium Safety and Performance in Respimat® (TIOSPIR®) compared the safety and efficacy of tiotropium Respimat® and tiotropium HandiHaler® in patients with chronic obstructive pulmonary disease (COPD). A prespecified spirometry substudy compared the lung function efficacy between...

  14. Food safety management systems performance in the lamb production chain

    NARCIS (Netherlands)

    Oses, S.M.; Luning, P.A.; Jacxsens, L.; Jaime, I.; Rovira, J.

    2012-01-01

    This study describes a performance measurement of implemented food safety management system (FSMS) along the lamb chain using an FSMS-diagnostic instrument (FSMS-DI) and a Microbiological Assessment Scheme (MAS). Three slaughterhouses, 1 processing plant and 5 butcher shops were evaluated. All the

  15. From Safety Culture to Culture for Safety — What is it that we Still Haven’t Learned

    International Nuclear Information System (INIS)

    Haber, S.B.

    2016-01-01

    In April 1986 the Chernobyl Accident happened. Several years later in 1991 the IAEA Independent Nuclear Safety Advisory Group published INSAG-4 and the concept of safety culture was defined for the nuclear community because of its relationship to the accident. Where the Three Mile Island Accident in 1979 had brought human factors issues in procedure development, human performance, and training to light, the Chernobyl Accident was discussed in terms of management, supervision, and safety culture. Work in the nuclear community evolved around the concept of safety culture although a clear understanding of what was actually meant was often missing. Methods to evaluate and assess safety culture were developed and efforts to integrate the findings of those evaluations into more traditional nuclear tools, such as probabilistic risk and safety assessment were attempted as well. Safety culture became thought of as a process that could be written into a procedure, measured by performance indicators and fixed in a corrective action program. The changes that organizations saw as a function of their safety culture improvement programs though were often just changes in some behaviors. Short term improvements in safety performance and the metrics to measure them were observed and many concluded they had really changed their safety culture. The changes were often not sustainable. The efforts did not include an in depth understanding of why individuals thought or behaved in the way that they did. In March 2011 the Fukushima Daiichi Accident happened. Initially it was accepted to explain it as a natural disaster. While the earthquake or the tsunami could not be prevented, there were things that could have been done before, during and immediately after the natural phenomena that would have helped to mitigate the consequences of the accident. The IAEA conducted an in-depth analysis of the human and organizational factors of that accident and drew a number of conclusions but none so

  16. W-1 Sodium Loop Safety Facility experiment centerline fuel thermocouple performance

    International Nuclear Information System (INIS)

    Meyers, S.C.; Henderson, J.M.

    1980-05-01

    The W-1 Sodium Loop Safety Facility (SLSF) experiment is the fifth in a series of experiments sponsored by the Department of Energy (DOE) as part of the National Fast Breeder Reactor (FBR) Safety Assurance Program. The experiments are being conducted under the direction of Argonne National Laboratory (ANL) and Hanford Engineering Development Laboratory (HEDL). The irradiation phase of the W-1 SLSF experiment was conducted between May 27 and July 20, 1979, and terminated with incipient fuel pin cladding failure during the final boiling transient. Experimental hardware and facility performed as designed, allowing completion of all planned tests and test objectives. This paper focuses on high temperature in-fuel thermocouples and discusses their development, fabrication, and performance in the W-1 experiment

  17. Development of NUMO safety case for geological disposal

    International Nuclear Information System (INIS)

    Suzuki, Satoru; Deguchi, Akira

    2016-01-01

    NUMO has developed a generic safety ease based on the latest knowledge to show the feasibility and safety of geological disposal in Japan. The NUMO safety case has been developed to provide a basic structure for subsequent safety cases that would be applied to any selected site, emphasising practical approaches and methodology, which will be applicable for the conditions/constraints during an actual siting process. This paper will provide a brief overview of the NUMO safety case. (author)

  18. Study on safety performance evaluation system of nuclear engineering construction units based on AHP

    International Nuclear Information System (INIS)

    Xu Yulin; Sun Jian; Shi Xiaofan

    2012-01-01

    As a very effectual management mean, the performance management has extensively used by many companies of China for staff assessment. The author explored the establishment of the 'Safety Performance Evaluation System' by finding out the similarities in operation between a company and a team of nuclear power projects. Then the author analyzed the principles of the performance management and good practices and summarized safety management experiences. The weight of the system index by using AHP method was calculated in this article. (authors)

  19. Key Performance Criteria Affecting the Most the Safety of a Nuclear Waste Long Term Storage : A Case Study Commissioned by CEA

    Energy Technology Data Exchange (ETDEWEB)

    Marvy, A.; Lioure, A; Heriard-Dubreuil, G.; Gadbois, S.; Schneider, T.; Schieber, C.

    2003-02-24

    As part of the work scope set in the French law on high level long lived waste R&D passed in 1991, CEA is conducting a research program to establish the scientific basis and assess the feasibility of long term storage as an option for the safe management of nuclear waste for periods as long as centuries. This goal is a significant departure from the current industrial practice where storage facilities are usually built to last only a few decades. From a technical viewpoint such an extension in time seems feasible provided care and maintenance is exercised. Considering such long periods of time, the risk for Society of loosing oversight and control of such a facility is real, which triggers the question of whether and how long term storage safety can be actually achieved. Therefore CEA commissioned a study (1) in which MUTADIS Consultants (2) and CEPN (3) were both involved. The case study looks into several past and actual human enterprises conducted over significant periods o f time, one of them dating back to the end of the 18th century, and all identified out of the nuclear field. Then-prevailing societal behavior and organizational structures are screened out to show how they were or are still able to cope with similar oversight and control goals. As a result, the study group formulated a set of performance criteria relating to issues like responsibility, securing funds, legal and legislative implications, economic sustainable development, all being areas which are not traditionally considered as far as technical studies are concerned. These criteria can be most useful from the design stage onward, first in an attempt to define the facility construction and operating guiding principles, and thereafter to substantiate the safety case for long term storage and get geared to the public dialogue on that undertaking should it become a reality.

  20. Key Performance Criteria Affecting the Most the Safety of a Nuclear Waste Long Term Storage : A Case Study Commissioned by CEA

    International Nuclear Information System (INIS)

    Marvy, A.; Lioure, A; Heriard-Dubreuil, G.; Gadbois, S.; Schneider, T.; Schieber, C.

    2003-01-01

    As part of the work scope set in the French law on high level long lived waste R and D passed in 1991, CEA is conducting a research program to establish the scientific basis and assess the feasibility of long term storage as an option for the safe management of nuclear waste for periods as long as centuries. This goal is a significant departure from the current industrial practice where storage facilities are usually built to last only a few decades. From a technical viewpoint such an extension in time seems feasible provided care and maintenance is exercised. Considering such long periods of time, the risk for Society of loosing oversight and control of such a facility is real, which triggers the question of whether and how long term storage safety can be actually achieved. Therefore CEA commissioned a study (1) in which MUTADIS Consultants (2) and CEPN (3) were both involved. The case study looks into several past and actual human enterprises conducted over significant periods o f time, one of them dating back to the end of the 18th century, and all identified out of the nuclear field. Then-prevailing societal behavior and organizational structures are screened out to show how they were or are still able to cope with similar oversight and control goals. As a result, the study group formulated a set of performance criteria relating to issues like responsibility, securing funds, legal and legislative implications, economic sustainable development, all being areas which are not traditionally considered as far as technical studies are concerned. These criteria can be most useful from the design stage onward, first in an attempt to define the facility construction and operating guiding principles, and thereafter to substantiate the safety case for long term storage and get geared to the public dialogue on that undertaking should it become a reality

  1. Nuclear criticality safety aspects of gaseous uranium hexafluoride (UF6) in the diffusion cascade

    International Nuclear Information System (INIS)

    Huffer, J.E.

    1997-04-01

    This paper determines the nuclear safety of gaseous UF 6 in the current Gaseous Diffusion Cascade and auxiliary systems. The actual plant safety system settings for pressure trip points are used to determine the maximum amount of HF moderation in the process gas, as well as the corresponding atomic number densities. These inputs are used in KENO V.a criticality safety models which are sized to the actual plant equipment. The ENO V.a calculation results confirm nuclear safety of gaseous UF 6 in plant operations

  2. Photovoltaic performance models: an evaluation with actual field data

    Science.gov (United States)

    TamizhMani, Govindasamy; Ishioye, John-Paul; Voropayev, Arseniy; Kang, Yi

    2008-08-01

    Prediction of energy production is crucial to the design and installation of the building integrated photovoltaic systems. This prediction should be attainable based on the commonly available parameters such as system size, orientation and tilt angle. Several commercially available as well as free downloadable software tools exist to predict energy production. Six software models have been evaluated in this study and they are: PV Watts, PVsyst, MAUI, Clean Power Estimator, Solar Advisor Model (SAM) and RETScreen. This evaluation has been done by comparing the monthly, seasonaly and annually predicted data with the actual, field data obtained over a year period on a large number of residential PV systems ranging between 2 and 3 kWdc. All the systems are located in Arizona, within the Phoenix metropolitan area which lies at latitude 33° North, and longitude 112 West, and are all connected to the electrical grid.

  3. Safety and performance indicators for the assessment of long-term safety of deep geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    Hugi, M.; Schneider, J.W.; Dorp, F. van; Zuidema, P.

    2005-01-01

    The evaluation of the ability to isolate radioactive waste and the assessment of the long-term safety of a deep geological repository is usually done in terms of the calculated dose and/or risk for an average individual of the population which is potentially most affected by the potential impacts of the repository. At present, various countries and international organisations are developing so-called complementary indicators to supplement such calculations. These indicators are called ''safety indicators'' if they refer to the safety of the whole repository system; if they address the isolation capability of individual system components or the whole system from a more technical perspective, they are called ''performance indicators''. The need for complementary indicators follows from the long time frames which characterise the safety assessment of a geological repository, and the corresponding uncertainty of the calculated radiation dose. The main reason for these uncertainties is associated with the uncertain long-term prognosis of the surface environment and the related human behaviour. (orig.)

  4. Modeling the Relationship between Safety Climate and Safety Performance in a Developing Construction Industry: A Cross-Cultural Validation Study.

    Science.gov (United States)

    Zahoor, Hafiz; Chan, Albert P C; Utama, Wahyudi P; Gao, Ran; Zafar, Irfan

    2017-03-28

    This study attempts to validate a safety performance (SP) measurement model in the cross-cultural setting of a developing country. In addition, it highlights the variations in investigating the relationship between safety climate (SC) factors and SP indicators. The data were collected from forty under-construction multi-storey building projects in Pakistan. Based on the results of exploratory factor analysis, a SP measurement model was hypothesized. It was tested and validated by conducting confirmatory factor analysis on calibration and validation sub-samples respectively. The study confirmed the significant positive impact of SC on safety compliance and safety participation , and negative impact on number of self-reported accidents/injuries . However, number of near-misses could not be retained in the final SP model because it attained a lower standardized path coefficient value. Moreover, instead of safety participation , safety compliance established a stronger impact on SP. The study uncovered safety enforcement and promotion as a novel SC factor, whereas safety rules and work practices was identified as the most neglected factor. The study contributed to the body of knowledge by unveiling the deviations in existing dimensions of SC and SP. The refined model is expected to concisely measure the SP in the Pakistani construction industry, however, caution must be exercised while generalizing the study results to other developing countries.

  5. Risk as a target of safety research

    International Nuclear Information System (INIS)

    Krueger, W.

    1986-01-01

    Job creation is not the idea behind the demand for risk studies to be intensified in safety research. Risks are not only a target safety research should investigate, they are a subject that actually can be most adequately investigated by safety research. Assuming a neutral position between irrational fears and interest-minded problem minimization, that is the central approach and the ethics of a safety scientist. The Babylonian confusion of terminology experienced after the Chernobyl accident is a good example proving the necessity of fostering the neutral professionalism in safety research. (orig./DG) [de

  6. The effect of Health, Safety and Environment Management System (HSE-MS on the improvement of safety performance indices in Urea and Ammonia Kermanshah Petrochemical Company

    Directory of Open Access Journals (Sweden)

    M. S. Poursoleiman

    2015-09-01

    .Conclusion: The implementation of Health, Safety and the Environment Management System caused a reduction in accidents and its consequences and most of the safety performance indices in the entire process cycle of Kermanshah Petrochemical Company. Overall, safety condition has been improved considerably.

  7. Performance and safety to NAVSEA instruction 9310.1A of lithium-thionyl chloride reserve batteries

    Science.gov (United States)

    Hall, J. C.

    1984-09-01

    The design, performance and safety of a fully engineered, selfcontained Li/SOCl2 battery as the power source for underwater applications. In addition to meeting the performance standards of the end user this battery is successfully tested under the rigorous safety conditions of NAVSEA Instruction 9310.1A for use on land, aircraft and surface ships.

  8. Human performance analysis in the frame of probabilistic safety assessment of research reactors

    International Nuclear Information System (INIS)

    Farcasiu, Mita; Nitoi, Mirela; Apostol, Minodora; Turcu, I.; Florescu, Gh.

    2005-01-01

    Full text: The analysis of operating experience has identified the importance of human performance in reliability and safety of research reactors. In Probabilistic Safety Assessment (PSA) of nuclear facilities, human performance analysis (HPA) is used in order to estimate human error contribution to the failure of system components or functions. HPA is a qualitative and quantitative analysis of human actions identified for error-likely situations or accident-prone situations. Qualitative analysis is used to identify all man-machine interfaces that can lead to an accident, types of human interactions which may mitigate or exacerbate the accident, types of human errors and performance shaping factors. Quantitative analysis is used to develop estimates of human error probability as effects of human performance in reliability and safety. The goal of this paper is to accomplish a HPA in the PSA frame for research reactors. Human error probabilities estimated as results of human actions analysis could be included in system event tree and/or system fault tree. The achieved sensitivity analyses determine human performance sensibility at systematically variations both for dependencies level between human actions and for operator stress level. The necessary information was obtained from operating experience of research reactor TRIGA from INR Pitesti. The required data were obtained from generic data bases. (authors)

  9. Road safety performance measures and AADT uncertainty from short-term counts.

    Science.gov (United States)

    Milligan, Craig; Montufar, Jeannette; Regehr, Jonathan; Ghanney, Bartholomew

    2016-12-01

    The objective of this paper is to enable better risk analysis of road safety performance measures by creating the first knowledge base on uncertainty surrounding annual average daily traffic (AADT) estimates when the estimates are derived by expanding short-term counts with the individual permanent counter method. Many road safety performance measures and performance models use AADT as an input. While there is an awareness that the input suffers from uncertainty, the uncertainty is not well known or accounted for. The paper samples data from a set of 69 permanent automatic traffic recorders in Manitoba, Canada, to simulate almost 2 million short-term counts over a five year period. These short-term counts are expanded to AADT estimates by transferring temporal information from a directly linked nearby permanent count control station, and the resulting AADT values are compared to a known reference AADT to compute errors. The impacts of five factors on AADT error are considered: length of short-term count, number of short-term counts, use of weekday versus weekend counts, distance from a count to its expansion control station, and the AADT at the count site. The mean absolute transfer error for expanded AADT estimates is 6.7%, and this value varied by traffic pattern group from 5% to 10.5%. Reference percentiles of the error distribution show that almost all errors are between -20% and +30%. Error decreases substantially by using a 48-h count instead of a 24-h count, and only slightly by using two counts instead of one. Weekday counts are superior to weekend counts, especially if the count is only 24h. Mean absolute transfer error increases with distance to control station (elasticity 0.121, p=0.001), and increases with AADT (elasticity 0.857, proad safety performance measures that use AADT as inputs. Analytical frameworks for such analysis exist but are infrequently used in road safety because the evidence base on AADT uncertainty is not well developed. Copyright

  10. Safety goals - a vital challenge to our society

    International Nuclear Information System (INIS)

    Schneider, T.

    1987-01-01

    In the past decades systematic approaches and tools to analyze the technical aspects of safety problems have been developed and continuously improved. We summarize these tools under the term of risk analysis. If applied in a proper and sensible way risk analysis helps technical experts to gain considerably better understanding of the performance of technical systems. Today the main open questions concerning safety are not technical ones. We hear complaints from many different sides concerning the actual handling of technological risks, but the efforts to change this situation are still rather limited. The author makes some rather general comments on today's situation and on some ideas about what we could and maybe should do for further progress. In addition he illustrates what kind of considerations seems necessary. (orig./HSCH)

  11. Verification and validation issues for digitally-based NPP safety systems

    International Nuclear Information System (INIS)

    Ets, A.R.

    1993-01-01

    The trend toward standardization, integration and reduced costs has led to increasing use of digital systems in reactor protection systems. While digital systems provide maintenance and performance advantages, their use also introduces new safety issues, in particular with regard to software. Current practice relies on verification and validation (V and V) to ensure the quality of safety software. However, effective V and V must be done in conjunction with a structured software development process and must consider the context of the safety system application. This paper present some of the issues and concerns that impact on the V and V process. These include documentation of systems requirements, common mode failures, hazards analysis and independence. These issues and concerns arose during evaluations of NPP safety systems for advanced reactor designs and digital I and C retrofits for existing nuclear plants in the United States. The pragmatic lessons from actual systems reviews can provide a basis for further refinement and development of guidelines for applying V and V to NPP safety systems. (author). 14 refs

  12. A proposal for performing software safety hazard analysis

    International Nuclear Information System (INIS)

    Lawrence, J.D.; Gallagher, J.M.

    1997-01-01

    Techniques for analyzing the safety and reliability of analog-based electronic protection systems that serve to mitigate hazards in process control systems have been developed over many years, and are reasonably understood. An example is the protection system in a nuclear power plant. The extension of these techniques to systems which include digital computers is not well developed, and there is little consensus among software engineering experts and safety experts on how to analyze such systems. One possible technique is to extend hazard analysis to include digital computer-based systems. Software is frequently overlooked during system hazard analyses, but this is unacceptable when the software is in control of a potentially hazardous operation. In such cases, hazard analysis should be extended to fully cover the software. A method for performing software hazard analysis is proposed in this paper. The method concentrates on finding hazards during the early stages of the software life cycle, using an extension of HAZOP

  13. Developing safety performance functions incorporating reliability-based risk measures.

    Science.gov (United States)

    Ibrahim, Shewkar El-Bassiouni; Sayed, Tarek

    2011-11-01

    Current geometric design guides provide deterministic standards where the safety margin of the design output is generally unknown and there is little knowledge of the safety implications of deviating from these standards. Several studies have advocated probabilistic geometric design where reliability analysis can be used to account for the uncertainty in the design parameters and to provide a risk measure of the implication of deviation from design standards. However, there is currently no link between measures of design reliability and the quantification of safety using collision frequency. The analysis presented in this paper attempts to bridge this gap by incorporating a reliability-based quantitative risk measure such as the probability of non-compliance (P(nc)) in safety performance functions (SPFs). Establishing this link will allow admitting reliability-based design into traditional benefit-cost analysis and should lead to a wider application of the reliability technique in road design. The present application is concerned with the design of horizontal curves, where the limit state function is defined in terms of the available (supply) and stopping (demand) sight distances. A comprehensive collision and geometric design database of two-lane rural highways is used to investigate the effect of the probability of non-compliance on safety. The reliability analysis was carried out using the First Order Reliability Method (FORM). Two Negative Binomial (NB) SPFs were developed to compare models with and without the reliability-based risk measures. It was found that models incorporating the P(nc) provided a better fit to the data set than the traditional (without risk) NB SPFs for total, injury and fatality (I+F) and property damage only (PDO) collisions. Copyright © 2011 Elsevier Ltd. All rights reserved.

  14. Health, safety and environmental unit performance assessment model under uncertainty (case study: steel industry).

    Science.gov (United States)

    Shamaii, Azin; Omidvari, Manouchehr; Lotfi, Farhad Hosseinzadeh

    2017-01-01

    Performance assessment is a critical objective of management systems. As a result of the non-deterministic and qualitative nature of performance indicators, assessments are likely to be influenced by evaluators' personal judgments. Furthermore, in developing countries, performance assessments by the Health, Safety and Environment (HSE) department are based solely on the number of accidents. A questionnaire is used to conduct the study in one of the largest steel production companies in Iran. With respect to health, safety, and environment, the results revealed that control of disease, fire hazards, and air pollution are of paramount importance, with coefficients of 0.057, 0.062, and 0.054, respectively. Furthermore, health and environment indicators were found to be the most common causes of poor performance. Finally, it was shown that HSE management systems can affect the majority of performance safety indicators in the short run, whereas health and environment indicators require longer periods of time. The objective of this study is to present an HSE-MS unit performance assessment model in steel industries. Moreover, we seek to answer the following question: what are the factors that affect HSE unit system in the steel industry? Also, for each factor, the extent of impact on the performance of the HSE management system in the organization is determined.

  15. Progress report on safety research of high-level waste management for the period April 1987 to March 1988

    International Nuclear Information System (INIS)

    Nakamura, Haruto; Tashiro, Shingo

    1988-10-01

    Researches on high-level waste management at the High Level Waste Management Laboratory and the Waste Safety Testing Facility Operation Division of the Japan Atomic Energy Research Institute in the fiscal year of 1987 are reviewed in the three sections of the report. The topics are as follows: 1) On performance and durability of waste forms and engineered barrier materials, accelerated alpha radiation stability of glass form and Synroc has been investigated and stress corrosion cracking of canister materials was examined under simulated conditions. 2) Sorption of 237 Np on granite samples and behavior of iron during weathering of granites were studied with respect to safety evaluation for geological disposal. 3) Actual waste was transported from the Tokai Reprocessing Plant and hot operation using the actual waste was initiated at WASTEF. (author)

  16. A Microbial Assessment Scheme to measure microbial performance of Food Safety Management Systems.

    Science.gov (United States)

    Jacxsens, L; Kussaga, J; Luning, P A; Van der Spiegel, M; Devlieghere, F; Uyttendaele, M

    2009-08-31

    A Food Safety Management System (FSMS) implemented in a food processing industry is based on Good Hygienic Practices (GHP), Hazard Analysis Critical Control Point (HACCP) principles and should address both food safety control and assurance activities in order to guarantee food safety. One of the most emerging challenges is to assess the performance of a present FSMS. The objective of this work is to explain the development of a Microbial Assessment Scheme (MAS) as a tool for a systematic analysis of microbial counts in order to assess the current microbial performance of an implemented FSMS. It is assumed that low numbers of microorganisms and small variations in microbial counts indicate an effective FSMS. The MAS is a procedure that defines the identification of critical sampling locations, the selection of microbiological parameters, the assessment of sampling frequency, the selection of sampling method and method of analysis, and finally data processing and interpretation. Based on the MAS assessment, microbial safety level profiles can be derived, indicating which microorganisms and to what extent they contribute to food safety for a specific food processing company. The MAS concept is illustrated with a case study in the pork processing industry, where ready-to-eat meat products are produced (cured, cooked ham and cured, dried bacon).

  17. Does employee safety influence customer satisfaction? Evidence from the electric utility industry.

    Science.gov (United States)

    Willis, P Geoffrey; Brown, Karen A; Prussia, Gregory E

    2012-12-01

    Research on workplace safety has not examined implications for business performance outcomes such as customer satisfaction. In a U.S. electric utility company, we surveyed 821 employees in 20 work groups, and also had access to archival safety data and the results of a customer satisfaction survey (n=341). In geographically-based work units where there were more employee injuries (based on archival records), customers were less satisfied with the service they received. Safety climate, mediated by safety citizenship behaviors (SCBs), added to the predictive power of the group-level model, but these two constructs exerted their influence independently from actual injuries. In combination, two safety-related predictor paths (injuries and climate/SCB) explained 53% of the variance in customer satisfaction. Results offer preliminary evidence that workplace safety influences customer satisfaction, suggesting that there are likely spillover effects between the safety environment and the service environment. Additional research will be needed to assess the specific mechanisms that convert employee injuries into palpable results for customers. Better safety climate and reductions in employee injuries have the potential to offer payoffs in terms of what customers experience. Copyright © 2012 National Safety Council and Elsevier Ltd. All rights reserved.

  18. Conducting organizational safety reviews - requirements, methods and experience

    International Nuclear Information System (INIS)

    Reiman, T.; Oedewald, P.; Wahlstroem, B.; Rollenhagen, C.; Kahlbom, U.

    2008-03-01

    Organizational safety reviews are part of the safety management process of power plants. They are typically performed after major reorganizations, significant incidents or according to specified review programs. Organizational reviews can also be a part of a benchmarking between organizations that aims to improve work practices. Thus, they are important instruments in proactive safety management and safety culture. Most methods that have been used for organizational reviews are based more on practical considerations than a sound scientific theory of how various organizational or technical issues influence safety. Review practices and methods also vary considerably. The objective of this research is to promote understanding on approaches used in organizational safety reviews as well as to initiate discussion on criteria and methods of organizational assessment. The research identified a set of issues that need to be taken into account when planning and conducting organizational safety reviews. Examples of the issues are definition of appropriate criteria for evaluation, the expertise needed in the assessment and the organizational motivation for conducting the assessment. The study indicates that organizational safety assessments involve plenty of issues and situations where choices have to be made regarding what is considered valid information and a balance has to be struck between focus on various organizational phenomena. It is very important that these choices are based on a sound theoretical framework and that these choices can later be evaluated together with the assessment findings. The research concludes that at its best, the organizational safety reviews can be utilised as a source of information concerning the changing vulnerabilities and the actual safety performance of the organization. In order to do this, certain basic organizational phenomena and assessment issues have to be acknowledged and considered. The research concludes with recommendations on

  19. Conducting organizational safety reviews - requirements, methods and experience

    Energy Technology Data Exchange (ETDEWEB)

    Reiman, T.; Oedewald, P.; Wahlstroem, B. [Technical Research Centre of Finland, VTT (Finland); Rollenhagen, C. [Royal Institute of Technology, KTH, (Sweden); Kahlbom, U. [RiskPilot (Sweden)

    2008-03-15

    Organizational safety reviews are part of the safety management process of power plants. They are typically performed after major reorganizations, significant incidents or according to specified review programs. Organizational reviews can also be a part of a benchmarking between organizations that aims to improve work practices. Thus, they are important instruments in proactive safety management and safety culture. Most methods that have been used for organizational reviews are based more on practical considerations than a sound scientific theory of how various organizational or technical issues influence safety. Review practices and methods also vary considerably. The objective of this research is to promote understanding on approaches used in organizational safety reviews as well as to initiate discussion on criteria and methods of organizational assessment. The research identified a set of issues that need to be taken into account when planning and conducting organizational safety reviews. Examples of the issues are definition of appropriate criteria for evaluation, the expertise needed in the assessment and the organizational motivation for conducting the assessment. The study indicates that organizational safety assessments involve plenty of issues and situations where choices have to be made regarding what is considered valid information and a balance has to be struck between focus on various organizational phenomena. It is very important that these choices are based on a sound theoretical framework and that these choices can later be evaluated together with the assessment findings. The research concludes that at its best, the organizational safety reviews can be utilised as a source of information concerning the changing vulnerabilities and the actual safety performance of the organization. In order to do this, certain basic organizational phenomena and assessment issues have to be acknowledged and considered. The research concludes with recommendations on

  20. Defining initiating events for purposes of probabilistic safety assessment

    International Nuclear Information System (INIS)

    1993-09-01

    This document is primarily directed towards technical staff involved in the performance or review of plant specific Probabilistic Safety Assessment (PSA). It highlights different approaches and provides typical examples useful for defining the Initiating Events (IE). The document also includes the generic initiating event database, containing about 300 records taken from about 30 plant specific PSAs. In addition to its usefulness during the actual performance of a PSA, the generic IE database is of the utmost importance for peer reviews of PSAs, such as the IAEA's International Peer Review Service (IPERS) where reference to studies on similar NPPs is needed. 60 refs, figs and tabs

  1. Performance evaluation methods and instrumentation for mine ventilation fans

    Institute of Scientific and Technical Information of China (English)

    LI Man; WANG Xue-rong

    2009-01-01

    Ventilation fans are one of the most important pieces of equipment in coal mines. Their performance plays an important role in the safety of staff and production. Given the actual requirements of coal mine production, we instituted a research project on the measurement methods of key performance parameters such as wind pressure, amount of ventilation and power. At the end a virtual instrument for mine ventilation fans performance evaluation was developed using a USB interface. The practical perform-ance and analytical results of our experiments show that it is feasible, reliable and effective to use the proposed instrumentation for mine ventilation performance evaluation.

  2. Development of performance tests for an automated MC and A system

    International Nuclear Information System (INIS)

    Kok, K.D.; Klingensmith, R.W.; Riffle, W.; Carver, R.D.; Schumacher, S.S.; Lavender, J.C.; Smith, B.W.

    1988-01-01

    Performance tests of MC and A systems using computers are described, and some example scenarios are discussed. Facility personnel or an external inspection group may use performance tests to evaluate MC and A capabilities under actual operating conditions. This paper addresses test elements common to both user groups. Performance tests consist of scenario development, security, and safety measures, conduct, and evaluation. Because exercises often test scenarios against which the MC and A system is protecting, they may require additional security and safety measures. Computer systems enhance MC and A by providing greater speed, increased precision, and automated checks. Performance tests for MC and A systems using computers differ from performance tests employing manual data systems in that the scenarios must anticipate computer actions rather than utilize controllers to adjust the scenario

  3. The performance regulatory approach in quality assurance: Its application to safety in nuclear power plants

    International Nuclear Information System (INIS)

    Sajaroff, Pedro M.

    2000-01-01

    In early 1991, the IAEA assembled an Advisory Group on the Comprehensive Revision of the Code and the Safety on Quality Assurance of the NUSS Programme. The Group was made up by specialists from a number of countries and from ISO, FORATOM, the EC and the IAEA itself, and its objective was completed in June 1995. This paper is aimed at describing the conceptual contents of the final draft of the revision 2 of the 50-C-QA Code 'Quality Assurance for Safety in Nuclear Power Plants and other Nuclear Facilities' (hereinafter, the Code) which is essentially based on performance. Although the performance regulatory approach is not new in Argentina and in other countries, what is indeed novel is applying performance based QA. In such a way the Code will contribute to preventing both QA misinterpretations (i.e., a formalistic regulatory requirement) and the execution of non-effective work without attaining the needed quality level (what may be seen as a pathological deviation of QA). The Code contains ten basic requirements to be adopted when QA programmes are established and implemented in nuclear power plants. The goal is improving safety through an improvement in the methods applied for attaining quality. In line with the current developments in quality management techniques, priority is given to effectiveness of the QA programme. All the involved individuals (that is those in the managerial level, those performing the work and those assessing the work performed) must contribute to quality in a co-ordinated manner. The revised Safety Guides are being introduced, standing out those non existing before. Interrelation between quality assurance, safety culture and quality culture is to be noted. Besides QA for safety-related software mentioned as an issue to be considered by the IAEA. (author)

  4. Yearly program of safety research for nuclear facilities and others

    International Nuclear Information System (INIS)

    1987-01-01

    The development of FBRs in Japan has steadily progressed, and subsequently to the experimental reactor 'Joyo' and the prototype reactor 'Monju', by promoting the construction of a demonstration reactor, the stage of verifying and acquiring skill of the electricity generation plant technology of practical scale, improving the performance and establishing the economical efficiency is about to begin. The development of FBRs in Japan has been advanced independently as a national project, and the method of preventing accidents in the actual reactors has been thoroughly taken. 'On the way of thinking in the safety evaluation of FBRs' was decided by the Nuclear Safety Commission. When the safety research from 1987 is systematized, as the constituents of safety logic, the way of thinking of the defense in depth, the way of thinking of the classification according to importance, the way of thinking of multilayer barriers against radioactive substances, and the way of thinking on severe accidents were investigated. The research concerning the decision of safety design and evaluation policy, and the safety research regarding accident prevention and relaxation, accident evaluation and severe accidents are reported. (Kako, I.)

  5. Training courses on integrated safety assessment modelling for waste repositories

    International Nuclear Information System (INIS)

    Mallants, D.

    2007-01-01

    Near-surface or deep repositories of radioactive waste are being developed and evaluated all over the world. Also, existing repositories for low- and intermediate-level waste often need to be re-evaluated to extend their license or to obtain permission for final closure. The evaluation encompasses both a technical feasibility as well as a safety analysis. The long term safety is usually demonstrated by means of performance or safety assessment. For this purpose computer models are used that calculate the migration of radionuclides from the conditioned radioactive waste, through engineered barriers to the environment (groundwater, surface water, and biosphere). Integrated safety assessment modelling addresses all relevant radionuclide pathways from source to receptor (man), using in combination various computer codes in which the most relevant physical, chemical, mechanical, or even microbiological processes are mathematically described. SCK-CEN organizes training courses in Integrated safety assessment modelling that are intended for individuals who have either a controlling or supervising role within the national radwaste agencies or regulating authorities, or for technical experts that carry out the actual post-closure safety assessment for an existing or new repository. Courses are organised by the Department of Waste and Disposal

  6. Cooling Performance Characteristics of the Stack Thermal Management System for Fuel Cell Electric Vehicles under Actual Driving Conditions

    Directory of Open Access Journals (Sweden)

    Ho-Seong Lee

    2016-04-01

    Full Text Available The cooling performance of the stack radiator of a fuel cell electric vehicle was evaluated under various actual road driving conditions, such as highway and uphill travel. The thermal stability was then optimized, thereby ensuring stable operation of the stack thermal management system. The coolant inlet temperature of the radiator in the highway mode was lower than that associated with the uphill mode because the corresponding frontal air velocity was higher than obtained in the uphill mode. In both the highway and uphill modes, the coolant temperatures of the radiator, operated under actual road driving conditions, were lower than the allowable limit (80 °C; this is the maximum temperature at which stable operation of the stack thermal management system of the fuel cell electric vehicle could be maintained. Furthermore, under actual road driving conditions in uphill mode, the initial temperature difference (ITD between the coolant temperature and air temperature of the system was higher than that associated with the highway mode; this higher ITD occurred even though the thermal load of the system in uphill mode was greater than that corresponding to the highway mode. Since the coolant inlet temperature is expected to exceed the allowable limit (80 °C in uphill mode under higher ambient temperature with air conditioning system operation, the FEM design layout should be modified to improve the heat capacity. In addition, the overall volume of the stack cooling radiator is 52.2% higher than that of the present model and the coolant inlet temperature of the improved radiator is 22.7% lower than that of the present model.

  7. Numerical and experimental investigation on the performance of safety valves operating with different gases

    International Nuclear Information System (INIS)

    Dossena, V.; Marinoni, F.; Bassi, F.; Franchina, N.; Savini, M.

    2013-01-01

    A detailed analysis of the effect related to the expansion of different gases throughout safety relief valves is carried out both numerically and experimentally. The considered gases are air, argon and ethylene, representative of a wide range of specific heat ratios. A first experimental campaign performed in air and argon on a safety relief valve characterized by connection 1/2″ × 1″ and orifice designation D (diameter 10 mm) according to API 526 showed significant reduction both in disc lift and in exhausted mass flow rate, at the nominal overpressure, when operating with argon. In order to gain a deeper insight into the physics involved and to evaluate the valve behavior with other gases, an extensive numerical testing has been performed by means of an accurate CFD code based on discontinuous Galerkin formulation. Numerical results are at first validated against measurements obtained in air on a 2″ J 3″ safety relief valve proving a remarkable accuracy of the computational method. Then the validated solver is applied on the same computational grid using argon and ethylene as working fluids. The three gases are considered as thermally perfect gases. A critical discussion based on the numerical results allows to clarify the fluid dynamic and physical reasons causing the observed trends both in the opening force and in the discharge coefficient. The main conclusion is that particular care must be taken when a safety valve operates with a fluid characterized by a specific heat ratio greater than the one of the gas used during type testing. -- Highlights: ► Effects of different gases on the discharge capacity and operational characteristics on safety relief valves. ► Influence of different specific heat ratio on safety relief valves discharge coefficient. ► Skilful application of Discontinuous Galerkin CFD solver to safety valves performances prediction

  8. Acute and chronic safety and efficacy of dose dependent creatine nitrate supplementation and exercise performance

    OpenAIRE

    Galvan, Elfego; Walker, Dillon K.; Simbo, Sunday Y.; Dalton, Ryan; Levers, Kyle; O?Connor, Abigail; Goodenough, Chelsea; Barringer, Nicholas D.; Greenwood, Mike; Rasmussen, Christopher; Smith, Stephen B.; Riechman, Steven E.; Fluckey, James D.; Murano, Peter S.; Earnest, Conrad P.

    2016-01-01

    Background Creatine monohydrate (CrM) and nitrate are popular supplements for improving exercise performance; yet have not been investigated in combination. We performed two studies to determine the safety and exercise performance-characteristics of creatine nitrate (CrN) supplementation. Methods Study 1 participants (N?=?13) ingested 1.5?g CrN (CrN-Low), 3?g CrN (CrN-High), 5?g CrM or a placebo in a randomized, crossover study (7d washout) to determine supplement safety (hepatorenal and musc...

  9. Engaging Employees: The Importance of High-Performance Work Systems for Patient Safety.

    Science.gov (United States)

    Etchegaray, Jason M; Thomas, Eric J

    2015-12-01

    To develop and test survey items that measure high-performance work systems (HPWSs), report psychometric characteristics of the survey, and examine associations between HPWSs and teamwork culture, safety culture, and overall patient safety grade. We reviewed literature to determine dimensions of HPWSs and then asked executives to tell us which dimensions they viewed as most important for safety and quality. We then created a HPWSs survey to measure the most important HPWSs dimensions. We administered an anonymous, electronic survey to employees with direct patient care working at a large hospital system in the Southern United States and looked for linkages between HPWSs, culture, and outcomes. Similarities existed for the HPWS practices viewed as most important by previous researchers and health-care executives. The HPWSs survey was found to be reliable, distinct from safety culture and teamwork culture based on a confirmatory factor analysis, and was the strongest predictor of the extent to which employees felt comfortable speaking up about patient safety problems as well as patient safety grade. We used information from a literature review and executive input to create a reliable and valid HPWSs survey. Future research needs to examine whether HPWSs is associated with additional safety and quality outcomes.

  10. Operational safety performance indicator system - a management tool for the self assessment of safety and reliability of nuclear power plants

    International Nuclear Information System (INIS)

    Anil Kumar; Mandowara, S.L.; Mittal, S.

    2006-01-01

    Operational Safety Performance Indicator system is one of the self assessment tools for station management to monitor safety and reliability of nuclear power plants. It provides information to station management about the performance of various areas of the plants by means of different colours of relevant performance indicators. Such systems have been implemented at many nuclear power plants in the world and have been considered as strength during WANO Peer Review. IAEA had a Coordinated Research Programme (CRP) on this with several countries participating including India. In NPCIL this system has been implemented in KAPS about a year back and found very useful in identifying areas which needs to be given more attention. Based on the KAPS feedback Implementation of this system has been taken up in RAPS-3 and 4 and KGS-l and 2. (author)

  11. Optimization of CCGT power plant and performance analysis using MATLAB/Simulink with actual operational data.

    Science.gov (United States)

    Hasan, Naimul; Rai, Jitendra Nath; Arora, Bharat Bhushan

    2014-01-01

    In the Modern scenario, the naturally available resources for power generation are being depleted at an alarming rate; firstly due to wastage of power at consumer end, secondly due to inefficiency of various power system components. A Combined Cycle Gas Turbine (CCGT) integrates two cycles- Brayton cycle (Gas Turbine) and Rankine cycle (Steam Turbine) with the objective of increasing overall plant efficiency. This is accomplished by utilising the exhaust of Gas Turbine through a waste-heat recovery boiler to run a Steam Turbine. The efficiency of a gas turbine which ranges from 28% to 33% can hence be raised to about 60% by recovering some of the low grade thermal energy from the exhaust gas for steam turbine process. This paper is a study for the modelling of CCGT and comparing it with actual operational data. The performance model for CCGT plant was developed in MATLAB/Simulink.

  12. Context-aware system for pre-triggering irreversible vehicle safety actuators.

    Science.gov (United States)

    Böhmländer, Dennis; Dirndorfer, Tobias; Al-Bayatti, Ali H; Brandmeier, Thomas

    2017-06-01

    New vehicle safety systems have led to a steady improvement of road safety and a reduction in the risk of suffering a major injury in vehicle accidents. A huge leap forward in the development of new vehicle safety systems are actuators that have to be activated irreversibly shortly before a collision in order to mitigate accident consequences. The triggering decision has to be based on measurements of exteroceptive sensors currently used in driver assistance systems. This paper focuses on developing a novel context-aware system designed to detect potential collisions and to trigger safety actuators even before an accident occurs. In this context, the analysis examines the information that can be collected from exteroceptive sensors (pre-crash data) to predict a certain collision and its severity to decide whether a triggering is entitled or not. A five-layer context-aware architecture is presented, that is able to collect contextual information about the vehicle environment and the actual driving state using different sensors, to perform reasoning about potential collisions, and to trigger safety functions upon that information. Accident analysis is used in a data model to represent uncertain knowledge and to perform reasoning. A simulation concept based on real accident data is introduced to evaluate the presented system concept. Copyright © 2017 Elsevier Ltd. All rights reserved.

  13. Nuclear criticality safety aspects of gaseous uranium hexafluoride (UF{sub 6}) in the diffusion cascade

    Energy Technology Data Exchange (ETDEWEB)

    Huffer, J.E. [Parallax, Inc., Atlanta, GA (United States)

    1997-04-01

    This paper determines the nuclear safety of gaseous UF{sub 6} in the current Gaseous Diffusion Cascade and auxiliary systems. The actual plant safety system settings for pressure trip points are used to determine the maximum amount of HF moderation in the process gas, as well as the corresponding atomic number densities. These inputs are used in KENO V.a criticality safety models which are sized to the actual plant equipment. The ENO V.a calculation results confirm nuclear safety of gaseous UF{sub 6} in plant operations..

  14. Safety analysis of MOX fuels by fuel performance code

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Motoe [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-12-01

    Performance of plutonium rick mixed oxide fuels specified for the Reduced-Moderation Water Reactor (RMWR) has been analysed by modified fuel performance code. Thermodynamic properties of these fuels up to 120 GWd/t burnup have not been measured and estimated using existing uranium fuel models. Fission product release, pressure rise inside fuel rods and mechanical loads of fuel cans due to internal pressure have been preliminarily assessed based on assumed axial power distribution history, which show the integrity of fuel performance. Detailed evaluation of fuel-cladding interactions due to thermal expansion or swelling of fuel pellets due to high burnup will be required for safety analysis of mixed oxide fuels. Thermal conductivity and swelling of plutonium rich mixed oxide fuels shall be taken into consideration. (T. Tanaka)

  15. SafetyBarrierManager, a software tool to perform risk analysis using ARAMIS's principles

    DEFF Research Database (Denmark)

    Duijm, Nijs Jan

    2017-01-01

    of the ARAMIS project, Risø National Laboratory started developing a tool that could implement these methodologies, leading to SafetyBarrierManager. The tool is based on the principles of “safety‐barrier diagrams”, which are very similar to “bowties”, with the possibility of performing quantitative analysis......The ARAMIS project resulted in a number of methodologies, dealing with among others: the development of standard fault trees and “bowties”; the identification and classification of safety barriers; and including the quality of safety management into the quantified risk assessment. After conclusion....... The tool allows constructing comprehensive fault trees, event trees and safety‐barrier diagrams. The tool implements the ARAMIS idea of a set of safety barrier types, to which a number of safety management issues can be linked. By rating the quality of these management issues, the operational probability...

  16. Contribution of materials investigations and operating experience of reactor vessel internals to PWRs' safety, performance and reliability

    International Nuclear Information System (INIS)

    Lemaire, E.; Monteil, N.; Jardin, N.; Doll, M.

    2015-01-01

    The Reactor Pressure Vessel Internals (RVI) include all the components inside the pressure vessel, except the nuclear fuel, the rod cluster assemblies and the instrumentation. The RVI consist of bolted and welded structures that are divided into two sub-assemblies: the upper internals which are removed at every refueling outage and the lower internals which are systematically removed for inspection at every 10-year outage. The main functions of the RVI are to position the core, to support it, and to provide a coolant flow by channeling the fluid. Moreover, the lower internals contribute to a neutron protection of the reactor pressure vessel by absorbing most of the neutron flux from the core. Depending on their location and material composition, the RVI components can face different ageing phenomena, that are actual or potential (such as wear, fatigue, stress corrosion cracking, irradiation assisted stress corrosion cracking, hardening and loss of ductility due to neutron irradiation, irradiation creep and irradiation swelling). EDF has developed a strategy for managing ageing and demonstrating the capacity of the RVI to perform their design functions over 40 years of operation. This overall approach is periodically revisited to take into account the most recent knowledge obtained from the following main topics: Safety Analyses, Research-Development programs, In-Service Inspection (ISI) results, Maintenance programs and Metallurgical Examinations. Based on continuous improvements in those fields, the goal of this paper is to present the way that materials investigations and operating experience obtained on RVI are managed by EDF to improve RVI safety, performance and reliability. It is shown that a perspective of 60 years of operation of RVI components is supported by large Research-Development efforts combined with field experience. (authors)

  17. Key Performance Indicators in the Evaluation of the Quality of Radiation Safety Programs.

    Science.gov (United States)

    Schultz, Cheryl Culver; Shaffer, Sheila; Fink-Bennett, Darlene; Winokur, Kay

    2016-08-01

    Beaumont is a multiple hospital health care system with a centralized radiation safety department. The health system operates under a broad scope Nuclear Regulatory Commission license but also maintains several other limited use NRC licenses in off-site facilities and clinics. The hospital-based program is expansive including diagnostic radiology and nuclear medicine (molecular imaging), interventional radiology, a comprehensive cardiovascular program, multiple forms of radiation therapy (low dose rate brachytherapy, high dose rate brachytherapy, external beam radiotherapy, and gamma knife), and the Research Institute (including basic bench top, human and animal). Each year, in the annual report, data is analyzed and then tracked and trended. While any summary report will, by nature, include items such as the number of pieces of equipment, inspections performed, staff monitored and educated and other similar parameters, not all include an objective review of the quality and effectiveness of the program. Through objective numerical data Beaumont adopted seven key performance indicators. The assertion made is that key performance indicators can be used to establish benchmarks for evaluation and comparison of the effectiveness and quality of radiation safety programs. Based on over a decade of data collection, and adoption of key performance indicators, this paper demonstrates one way to establish objective benchmarking for radiation safety programs in the health care environment.

  18. TH-C-18C-01: MRI Safety

    Energy Technology Data Exchange (ETDEWEB)

    Pooley, R [Mayo Clinic, Jacksonville, FL (United States); Bernstein, M; Shu, Y; Gorny, K; Felmlee, J [Mayo Clinic, Rochester, MN (United States); Panda, A [Mayo Clinic, Arizona, Scottsdale, AZ (United States)

    2014-06-15

    Clinical diagnostic medical physicists may be responsible for implementing and maintaining a comprehensive MR safety program. Accrediting bodies including the ACR, IAC, Radsite and The Joint Commission each include aspects of MR Safety into their imaging accreditation programs; MIPPA regulations further raise the significance of non-compliance. In addition, The Joint Commission recently announced New and Revised Diagnostic Imaging Standards for accredited health care organizations which include aspects of MR Safety. Hospitals and clinics look to the physicist to understand guidelines, regulations and accreditation requirements related to MR safety. The clinical medical physicist plays a significant role in a clinical practice by understanding the physical basis for the risks and acting as a facilitator to successfully implement a safety program that provides well-planned siting, allows for the safe scanning of certain implanted devices, and helps radiologists manage specific patient exams. The MRI scanning of specific devices will be discussed including cardiac pacemakers and neurostimulators such as deep brain stimulators. Furthermore for sites involved in MR guided interventional procedures, the MR physicist plays an essential role to establish safe practices. Creating a framework for a safe MRI practice includes the review of actual safety incidents or close calls to determine methods for prevention in the future. Learning Objectives: Understand the requirements and recommendations related to MR safety from accrediting bodies and federal regulations. Understand the Medical Physicist's roles to ensure MR Safety. Identify best practices for dealing with implanted devices, including pacemakers and deep brain stimulators. Review aspects of MR safety involved in an MR guided interventional environment. Understand the important MR safety aspects in actual safety incidents or near misses.

  19. Operational safety performance and economical efficiency evaluation for nuclear power plants

    International Nuclear Information System (INIS)

    Liu Yachun; Zou Shuliang

    2012-01-01

    The economical efficiency of nuclear power includes a series of environmental parameters, for example, cleanliness. Nuclear security is the precondition and guarantee for its economy, and both are the direct embodiment of the social benefits of nuclear power. Through analyzing the supervision and management system on the effective operation of nuclear power plants, which has been put forward by the International Atomic Energy Agency (IAEA), the World Association of Nuclear Operators (WANO), the U.S. Nuclear Regulatory Commission (NRC), and other organizations, a set of indexs on the safety performance and economical efficiency of nuclear power are explored and established; Based on data envelopment analysis, a DEA approach is employed to evaluate the efficiency of the operation performance of several nuclear power plants, Some primary conclusion are achieved on the basis of analyzing the threshold parameter's sensitivity and relativity which affected operational performance. To address the conflicts between certain security and economical indicators, a multi-objective programming model is established, where top priority is given to nuclear safety, and the investment behavior of nuclear power plant is thereby optimized. (authors)

  20. The nuclear safety at Cattenom: when an anomaly becomes a fundamental problem

    International Nuclear Information System (INIS)

    Legrand, V.; Marignac, Y.

    2003-02-01

    The Cattenom nuclear power plant established in Moselle, near Luxembourg is the center of incidents that placed in the context of the actual management of its park by EDF are significant of a safety erosion, linked to the research of economic performance. More, the analysis of the management by the operator and its supervision authority of these incidents raises questions on their ability to evaluate, control and exchange information on these problems. (N.C.)

  1. Measuring Safety Culture on Ships Using Safety Climate: A Study among Indian Officers

    Directory of Open Access Journals (Sweden)

    Yogendra Bhattacharya

    2015-12-01

    Full Text Available Workplace safety continues to be an area of concern in the maritime industry due to the international nature of the operations. The effectiveness of extensive legislation to manage shipboard safety remains in doubt. The focus must therefore shift towards the human element - seafarers and their perceptions of safety. The study aims to understand the alignment that exists between safety culture and safety climate on board ships as perceived by seafarers. The underlying factors of safety climate were identified using factor analysis which isolated seven factors - Support on Safety, Organizational Support, Resource Availability, Work Environment, Job Demands, ‘Just’ Culture, and Safety Compliance. The perception of safety level of seafarers was found to be low indicating the existence of misalignments between safety culture values and the actual safety climate. The study also reveals that the safety perceptions of officers employed directly by ship owners and those by managers do not differ significantly, nor do they differ between senior and junior officers. A shift in perspective towards how seafarers themselves feel towards safety might provide more effective solutions – instead of relying on regulations - and indeed aid in reducing incidents on board. This paper details practical suggestions on how to identify the factors that contribute towards a better safety climate on board ships.

  2. Performance and Reliability of DSRC Vehicular Safety Communication: A Formal Analysis

    Directory of Open Access Journals (Sweden)

    2009-02-01

    Full Text Available IEEE- and ASTM-adopted dedicated short range communications (DSRC standard toward 802.11p is a key enabling technology for the next generation of vehicular safety communication. Broadcasting of safety messages is one of the fundamental services in DSRC. There have been numerous publications addressing design and analysis of such broadcast ad hoc system based on the simulations. For the first time, an analytical model is proposed in this paper to evaluate performance and reliability of IEEE 802.11a-based vehicle-to-vehicle (V2V safety-related broadcast services in DSRC system on highway. The proposed model takes two safety services with different priorities, nonsaturated message arrival, hidden terminal problem, fading transmission channel, transmission range, IEEE 802.11 backoff counter process, and highly mobile vehicles on highway into account. Based on the solutions to the proposed analytic model, closed-form expressions of channel throughput, transmission delay, and packet reception rates are derived. From the obtained numerical results under various offered traffic and network parameters, new insights and enhancement suggestions are given.

  3. Nuclear power performance and safety. V.5. Nuclear fuel cycle

    International Nuclear Information System (INIS)

    1988-01-01

    The International Conference on Nuclear Power Performance and Safety, organized by the International Atomic Energy Agency, was held at the Austria Centre Vienna (ACV) in Vienna, Austria, from 28 September to 2 October 1987. The objective of the Conference was to promote an exchange of worldwide information on the current trends in the performance and safety of nuclear power and its fuel cycle, and to take a forward look at the expectations and objectives for the 1990s. Policy decisions for waste management have already been taken in many countries and the 1990s should be a period of demonstration and implementation of these policies. As ilustrated by data presented from a number of countries, many years of experience in radioactive waste management have been achieved and the technology exists to implement the national plans and policies that have been developed. The establishment of criteria, the development of safety performance methodology and site investigation work are key activities essential to the successful selection, characterization and construction of geological repositories for the final disposal of radioactive waste. Considerable work has been done in these areas over the last ten years and will continue into the 1990s. However, countries that are considering geological disposal for high level waste now recognize the need for relating the technical aspects to public understanding and acceptance of the concept and decision making activities. The real challenge for the 1990s in waste disposal will be successfully to integrate technological activities within a process which responds to institutional and public concern. Volume 5 of the Proceedings comprehends the contributions on waste management in the 1990s. Decontamination and decommissioning, waste management, treatment and disposal, nuclear fuel cycle - present and future. Enrichment services and advanced reactor fuels, improvements in reactor fuel utilization and performance, spent fuel management

  4. NPP Krsko periodic safety review. Safety assessment and analyses

    International Nuclear Information System (INIS)

    Basic, I.; Spiler, J.; Thaulez, F.

    2002-01-01

    Definition of a PSR (Periodic Safety Review) project is a comprehensive safety review of a plant after ten years of operation. The objective is a verification by means of a comprehensive review using current methods that the plant remains safe when judged against current safety objectives and practices and that adequate arrangements are in place to maintain plant safety. The overall goals of the NEK PSR Program are defined in compliance with the basic role of a PSR and the current practice typical for most of the countries in EU. This practice is described in the related guides and good practice documents issued by international organizations. The overall goals of the NEK PSR are formulated as follows: to demonstrate that the plant is as safe as originally intended; to evaluate the actual plant status with respect to aging and wear-out identifying any structures, systems or components that could limit the life of the plant in the foreseeable future, and to identify appropriate corrective actions, where needed; to compare current level of safety in the light of modern standards and knowledge, and to identify where improvements would be beneficial for minimizing deviations at justifiable costs. The Krsko PSR will address the following safety factors: Operational Experience, Safety Assessment, EQ and Aging Management, Safety Culture, Emergency Planning, Environmental Impact and Radioactive Waste.(author)

  5. Perceptions of inpatient rehabilitation changes after the Centers for Medicare and Medicaid Service 2010 regulatory updates contrasted with actual performance.

    Science.gov (United States)

    Riggs, Richard V; Roberts, Pamela S; DiVita, Margaret A; Niewczyk, Paulette; Granger, Carl V

    2014-01-01

    To compare and contrast subjective perceptions with objective compliance of the impact of the 2010 Centers for Medicare and Medicaid Service updates of the Medicare Benefit Policy Manual. Cross-sectional survey. An electronic survey was sent by the Uniform Data System for Medical Rehabilitation to all enrolled inpatient rehabilitation facility subscribers (n = 817). The survey was sent April 15, 2011, and responses were tabulated if they were received by May 15, 2011. Comparing and contrasting of the subjective perception to objective evaluation and/or compliance with the Medicare Benefit Policy Manual on case mix index, length of stay, admissions by diagnostic category as well as perception of preadmission screening, postadmission evaluation, plan of care, and interdisciplinary conferencing. Twenty-five percent of the 817 facilities responded, for a total of 209 responses. Complete data were present in 148 of the respondents. For most diagnostic categories, perception of change did not mirror reality of change; neither did the perception between change in case mix index and length of stay. Perception did match reality in stroke and multiple trauma cases; respondents perceived an increase in admissions for the 2 impairments, and there was an overall increase in reality. Comparison with actual data identified that gaps exist between diagnostic category perceptions and actual diagnostic category admission performance. Regulations such as the 75%-60% rule and audit focus on non-neurologic conditions as well as actual inpatient rehabilitation facility program payment reports may have influenced respondents perceptions to change associated with the Medicare Benefit Policy Manual modifications. This disparity between perception and actual data may have implications for programmatic planning, forecasting, and resource allocation. Copyright © 2014 American Academy of Physical Medicine and Rehabilitation. Published by Elsevier Inc. All rights reserved.

  6. Danish Sector Guide for Calculation of the Actual Energy Consumption

    DEFF Research Database (Denmark)

    Mortensen, Lone Hedegaard

    2016-01-01

    , the innovation network for sustainable construction, InnoBYG started work on a Danish sector guide for the calculation of actual energy consumption in relation to upgrading of buildings. The focus was to make a common guide for energy calculations that can be used by consultants performing calculations...... consumption compared with the estimated energy demand by calculation. The paper concludes that the result of an energy calculation should not be given as a single figure but rather as a spread between the best and worst case for the assumed conditions. Finally, a brief update on current actions is given...... related to the sector guide for calculation of actual energy consumption. Keywords – Energy calculations, actual energy consumption, energy perfomance...

  7. Key performance outcomes of patient safety curricula: root cause analysis, failure mode and effects analysis, and structured communications skills.

    Science.gov (United States)

    Fassett, William E

    2011-10-10

    As colleges and schools of pharmacy develop core courses related to patient safety, course-level outcomes will need to include both knowledge and performance measures. Three key performance outcomes for patient safety coursework, measured at the course level, are the ability to perform root cause analyses and healthcare failure mode effects analyses, and the ability to generate effective safety communications using structured formats such as the Situation-Background-Assessment-Recommendation (SBAR) situational briefing model. Each of these skills is widely used in patient safety work and competence in their use is essential for a pharmacist's ability to contribute as a member of a patient safety team.

  8. Dynamics of safety performance and culture: a group model building approach.

    Science.gov (United States)

    Goh, Yang Miang; Love, Peter E D; Stagbouer, Greg; Annesley, Chris

    2012-09-01

    The management of occupational health and safety (OHS) including safety culture interventions is comprised of complex problems that are often hard to scope and define. Due to the dynamic nature and complexity of OHS management, the concept of system dynamics (SD) is used to analyze accident prevention. In this paper, a system dynamics group model building (GMB) approach is used to create a causal loop diagram of the underlying factors influencing the OHS performance of a major drilling and mining contractor in Australia. While the organization has invested considerable resources into OHS their disabling injury frequency rate (DIFR) has not been decreasing. With this in mind, rich individualistic knowledge about the dynamics influencing the DIFR was acquired from experienced employees with operations, health and safety and training background using a GMB workshop. Findings derived from the workshop were used to develop a series of causal loop diagrams that includes a wide range of dynamics that can assist in better understanding the causal influences OHS performance. The causal loop diagram provides a tool for organizations to hypothesize the dynamics influencing effectiveness of OHS management, particularly the impact on DIFR. In addition the paper demonstrates that the SD GMB approach has significant potential in understanding and improving OHS management. Copyright © 2011 Elsevier Ltd. All rights reserved.

  9. Development of the NUMO pre-selection, site-specific safety case

    International Nuclear Information System (INIS)

    Fujiyama, Tetsuo; Suzuki, Satoru; Deguchi, Akira; Umeki, Hiroyuki

    2016-01-01

    Key conclusions: ◆ “The NUMO pre-selection, site-specific safety case” provides the basic structure for subsequent safety cases that will be applied to any selected site, emphasising practical approaches and methodology which will be applicable for the conditions/constraints during an actual siting process. ◆ The preliminary results of the design and safety assessment would underpin the feasibility and safety of geological disposal in Japan.

  10. Leading safety performance indicators for resilience assessment of radiopharmaceuticals production process

    International Nuclear Information System (INIS)

    Grecco, Claudio H.S.; Santos, Isaac J.A.L.; Carvalho, Paulo V.R.

    2011-01-01

    Radiopharmaceuticals are radiation-emitting substances used in medicine for radiotherapy and imaging diagnosis. A Research Institute, located in Rio de Janeiro, produces three radiopharmaceuticals: the sodium iodate is used in the diagnosis of thyroid dysfunctions, the meta-iodo-benzyl guanidine is used in the diagnosis of cardiac diseases, and the fluorodeoxyglucose is used in diagnosis in cardiology, oncology, neurology and neuro psychiatry. This paper presents a leading safety performance indicators framework to assess the resilience of radiopharmaceuticals production processes. The organizations that use resilience indicators will be able to pro actively evaluate and manage safety. (author)

  11. Leading safety performance indicators for resilience assessment of radiopharmaceuticals production process

    Energy Technology Data Exchange (ETDEWEB)

    Grecco, Claudio H.S.; Santos, Isaac J.A.L.; Carvalho, Paulo V.R., E-mail: grecco@ien.gov.b, E-mail: luquetti@ien.gov.b, E-mail: paulov@ien.gov.b [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Div. de Instrumentacao e Confiabilidade Humana; Vidal, Mario C.R., E-mail: mvidal@ergonomia.ufrj.b [Coordenacao dos Programas de Pos-Graduacao de Engenharia (PEP/COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia de Producao. Grupo de Ergonomia e Novas Tecnologias (GENTE)

    2011-07-01

    Radiopharmaceuticals are radiation-emitting substances used in medicine for radiotherapy and imaging diagnosis. A Research Institute, located in Rio de Janeiro, produces three radiopharmaceuticals: the sodium iodate is used in the diagnosis of thyroid dysfunctions, the meta-iodo-benzyl guanidine is used in the diagnosis of cardiac diseases, and the fluorodeoxyglucose is used in diagnosis in cardiology, oncology, neurology and neuro psychiatry. This paper presents a leading safety performance indicators framework to assess the resilience of radiopharmaceuticals production processes. The organizations that use resilience indicators will be able to pro actively evaluate and manage safety. (author)

  12. An innovative program to increase safety culture for workers on a nuclear power plant

    International Nuclear Information System (INIS)

    Schryvers, Vincent

    2007-01-01

    Full text: To implement the WENRA harmonized guidelines and the IAEA reference guides, Electrabel has recently introduced a major training program for both its own staff and the contractors working on the sites of its Nuclear Power Plants. This training program stresses the importance of safety culture on both theoretical and practical level and is mostly focused on the behavioural aspects during activities performed at the site of a Nuclear Power Plant. Further emphasis is put on radiation protection, industrial safety, environmental protection and explosion prevention. The training scheme for both the staff of Electrabel and contractors typically contains a theoretical part introducing the basic concepts of nuclear safety and safety culture and a practical exercise in a simulated environment. A novel element in the training cycle is the use of a simulated environment, where the actual working conditions in the nuclear part of the installation are simulated. This mock-up installation enables the workers to train the nuclear safety constraints linked to the actual installation and to enhance safety culture by responding on simulated problems and changing conditions possibly being encountered during an intervention at the real working site. To analyze the behaviour of the future workers, the activities are videotaped and commented for further improvement. A refresh of the training courses is implemented after 3 years.Although this training program has only been in operation for just 6 months, the response of the contractors and the staff to this training has been enthusiastic. At this moment, more than 1.000 workers have successfully completed the training course. (author)

  13. Benchmarking road safety performances of countries.

    NARCIS (Netherlands)

    Wegman, F.C.M. & Oppe, S.

    2014-01-01

    In order to obtain political interest in road safety problems and to learn from other countries’ ‘good practices’, it is often helpful to compare one’s own safety situation with that of other countries. In a number of projects tools have been developed for such comparisons. These tools range from

  14. Breeder design for enhanced performance and safety characteristics

    International Nuclear Information System (INIS)

    Fischer, G.J.; Atefi, B.; Yang, J.W.; Galperin, A.; Segev, M.

    1980-01-01

    A fast breeder reactor design has been created which offers a considerably extended fuel cycle and excellent performance characteristics. An example of a core designed to operate on a ten-year fuel cycle is described in some detail. Use of metal fuel along with a moderator such as beryllium oxide dispersed throughout the core provides both design flexibility and safety advantages such as a strong Doppler feedback and limited sodium void reactivity gain. Local power variations are small for the entire cycle; control requirements are also modest, and fuel cycle costs are low

  15. Safety assessment in plant layout design using indexing approach: implementing inherent safety perspective. Part 2-Domino Hazard Index and case study.

    Science.gov (United States)

    Tugnoli, Alessandro; Khan, Faisal; Amyotte, Paul; Cozzani, Valerio

    2008-12-15

    The design of layout plans requires adequate assessment tools for the quantification of safety performance. The general focus of the present work is to introduce an inherent safety perspective at different points of the layout design process. In particular, index approaches for safety assessment and decision-making in the early stages of layout design are developed and discussed in this two-part contribution. Part 1 (accompanying paper) of the current work presents an integrated index approach for safety assessment of early plant layout. In the present paper (Part 2), an index for evaluation of the hazard related to the potential of domino effects is developed. The index considers the actual consequences of possible escalation scenarios and scores or ranks the subsequent accident propagation potential. The effects of inherent and passive protection measures are also assessed. The result is a rapid quantification of domino hazard potential that can provide substantial support for choices in the early stages of layout design. Additionally, a case study concerning selection among various layout options is presented and analyzed. The case study demonstrates the use and applicability of the indices developed in both parts of the current work and highlights the value of introducing inherent safety features early in layout design.

  16. Performance Test Results of Safety I and C Systems of SMART MMIS

    International Nuclear Information System (INIS)

    Suh, Yong Suk; Keum, Jong Yong; Jeong, Kwang Il; Lee, Joon Ku; Lee, Sang Seok; Kim, Kwan Woong

    2011-01-01

    KAERI has developed SMART (System-integrated Modular Advanced ReacTor), a 330MWt integral pressurized light water reactor that integrates four reactor coolant pumps, one pressurizer, eight steam generators, and one reactor core into a reactor vessel, since 1997 and submitted a SSAR (Standard design Safety Analysis Report) to Korea institute of nuclear safety (KINS) at the end of 2010 for the purpose of achieving the standard design approval (SDA) by the end of 2011. SMART MMIS has been designed with fully digitalized systems. Non-safety instrumentation and control (I and C) systems are designed based on the commercial distributed control systems. The safety I and C systems are designed using a new platform that was developed and validated by KAERI. Safety I and C systems are modularized using the platform. In the protection systems (PSs), datalinks are used to transmit data in a one-way direction in order to meet the independency requirement. In the engineered safety features-component control system (ESF-CCS), network switch devices (NSDs) are used to connect the group and loop controllers. The NSD was also newly developed and validated by KAERI. After validating the platform and NSD, a test facility was developed using the platform and NSDs to validate the performance of safety I and C systems. This paper presents the development and test results from the test facility

  17. Safety and performance assessment of geologic disposal systems for nuclear wastes

    International Nuclear Information System (INIS)

    Peltonen, E.

    1987-01-01

    This thesis presents a methodology for the safety and performance assesment of final disposal of nuclear wastes into crystalline bedrock. The applicability of radiation protection objectives is discussed, as well as the goals of the assessment in the various repository system development phases. Due consideration is given to the description of the pertinent analysis methods and to the comprehensive model system. The methodology has been applied to assess the acceptability of the basic disposal concepts and to study the possibilities for the optimization of protection. Furthermore, performance of different components in the multiple barrier disposal systems is estimated. The waste types dealt with are low- and intermediate-level waste as well as high-level spent nuclear fuel from a nuclear power plant. In addition, an option of high-level vitrified waste from reprocessing of spent fuel is taken into account. On the basis of the various analyses carried out it can be concluded that the disposal of different nuclear wastes in the Finnish bedrock in properly designed repositories meets the radiation protection objectives with good confidence. In addition, the studies indicate that the safety margins are considerable. This is due to the fact that the overall performance of the multiple barrier disposal systems analysed is not sensitive to possible unfavourable changes in barrier properties. From the optimization of protection point of view it can be concluded that there is no need to develop more effective repository designs than those analysed in this thesis. In fact, the results indicate that the most sophisticated designs have already gone beyond an optimal level of safety

  18. Determination of performance criteria of safety systems in a nuclear power plant via simulated annealing optimization method

    International Nuclear Information System (INIS)

    Jung, Woo Sik

    1993-02-01

    This study presents and efficient methodology that derives design alternatives and performance criteria of safety functions/systems in commercial nuclear power plants. Determination of design alternatives and intermediate-level performance criteria is posed as a reliability allocation problem. The reliability allocation is performed for determination of reliabilities of safety functions/systems from top-level performance criteria. The reliability allocation is a very difficult multi objective optimization problem (MOP) as well as a global optimization problem with many local minima. The weighted Chebyshev norm (WCN) approach in combination with an improved Metropolis algorithm of simulated annealing is developed and applied to the reliability allocation problem. The hierarchy of probabilistic safety criteria (PSC) may consist of three levels, which ranges from the overall top level (e.g., core damage frequency, acute fatality and latent cancer fatality) through the interlnediate level (e.g., unavailiability of safety system/function) to the low level (e.g., unavailability of components, component specifications or human error). In order to determine design alternatives of safety functions/systems and the intermediate-level PSC, the reliability allocation is performed from the top-level PSC. The intermediated level corresponds to an objective space and the top level is related to a risk space. The reliability allocation is performed by means of a concept of two-tier noninferior solutions in the objective and risk spaces within the top-level PSC. In this study, two kinds of towtier noninferior solutions are defined: intolerable intermediate-level PSC and desirable design alternatives of safety functions/systems that are determined from Sets 1 and 2, respectively. Set 1 is obtained by maximizing simultaneously not only safety function/system unavailabilities but also risks. Set 1 reflects safety function/system unavailabilities in the worst case. Hence, the

  19. Performance of balanced bellows safety relief valves

    International Nuclear Information System (INIS)

    Lai, Y.S.

    1992-01-01

    By the nature of its design, the set point and lift of a conventional spring loaded safety relief valve are sensitive to back pressure. One way to reduce the adverse effects of the back pressure on the safety relief valve function is to install a balanced bellows in a safety relief valve. The metallic bellows has a rather wide range of manufacturing tolerance which makes the design of the bellows safety relief valve very complicated. The state-of-the-art balanced bellows safety relief valve can only substantially minimize, but cannot totally eliminate the back pressure effects on its set point and relieving capacity. Set point change is a linear function of the back pressure to the set pressure ratio. Depending on the valve design, the set point correction factor can be either greater or smaller than unity. There exists an allowable back pressure and critical back pressure for each safety relief valve. When total back pressure exceeds the R a , the relieving capacity will be reduced mainly resulting from the valve lift being reduced by the back pressure and the capacity reduction factor should be applied in valve sizing. Once the R c is exceeded, the safety relief valve becomes unstable and loses its over pressure protection capability. The capacity reduction factor is a function of system overpressure, but their relationship is non-linear in nature. (orig.)

  20. Safety guides development process in Spain

    International Nuclear Information System (INIS)

    Butragueno, J.L.; Perello, M.

    1979-01-01

    Safety guides have become a major factor in the licensing process of nuclear power plants and related nuclear facilities of the fuel cycle. As far as the experience corroborates better and better engineering methodologies and procedures, the results of these are settled down in form of standards, guides, and similar issues. This paper presents the actual Spanish experience in nuclear standards and safety guides development. The process to develop a standard or safety guide is shown. Up to date list of issued and on development nuclear safety guides is included and comments on the future role of nuclear standards in the licensing process are made. (author)

  1. A structural equation modelling approach examining the pathways between safety climate, behaviour performance and workplace slipping

    OpenAIRE

    Swedler, David I; Verma, Santosh K; Huang, Yueng-Hsiang; Lombardi, David A; Chang, Wen-Ruey; Brennan, Melayne; Courtney, Theodore K

    2015-01-01

    Objective: Safety climate has previously been associated with increasing safe workplace behaviours and decreasing occupational injuries. This study seeks to understand the structural relationship between employees’ perceptions of safety climate, performing a safety behaviour (ie, wearing slip-resistant shoes) and risk of slipping in the setting of limited-service restaurants. Methods: At baseline, we surveyed 349 employees at 30 restaurants for their perceptions of their safety training and m...

  2. Performance improvement of the Annular Core Pulse Reactor for reactor safety experiments

    International Nuclear Information System (INIS)

    Reuscher, J.A.; Pickard, P.S.

    1976-01-01

    The Annular Core Pulse Reactor (ACPR) is a TRIGA type reactor which has been in operation at Sandia Laboratories since 1967. The reactor is utilized in a wide variety of experimental programs which include radiation effects, neutron radiography, activation analysis, and fast reactor safety. During the past several years, the ACPR has become an important experimental facility for the United States Fast Reactor Safety Research Program and questions of interest to the safety of the LMFBR are being addressed. In order to enhance the capabilities of the ACPR for reactor safety experiments, a project to improve the performance of the reactor was initiated. It is anticipated that the pulse fluence can be increased by a factor of 2.0 to 2.5 utilizing a two-region core concept with high heat capacity fuel elements around the central irradiation cavity. In addition, the steady-state power of the reactor will be increased by about a factor of two. The new features of the improvements are described

  3. Survey and analysis of radiation safety management systems at medical institutions. Initial report. Radiation protection supervisor, radiation safety organization, and education and training

    International Nuclear Information System (INIS)

    Ohba, Hisateru; Ogasawara, Katsuhiko; Aburano, Tamio

    2005-01-01

    In this study, a questionnaire survey was carried out to determine the actual situation of radiation safety management systems in Japanese medical institutions with nuclear medicine facilities. The questionnaire consisted of questions concerning the Radiation Protection Supervisor license, safety management organizations, and problems related to education and training in safety management. Analysis was conducted according to region, type of establishment, and number of beds. The overall response rate was 60%, and no significant difference in response rate was found among regions. Medical institutions that performed nuclear medicine practices without a radiologist participating accounted for 10% of the total. Medical institutions where nurses gave patients intravenous injections of radiopharmaceuticals as part of the nuclear medicine practices accounted for 28% of the total. Of these medical institutions, 59% provided education and training in safety management for nurses. The rate of acquisition of Radiation Protection Supervisor licenses was approximately 70% for radiological technologists and approximately 20% for physicians (regional difference, p=0.02). The rate of medical institutions with safety management organizations was 71% of the total. Among the medical institutions (n=208) without safety management organizations, approximately 56% had 300 beds or fewer. In addition, it became clear that 35% of quasi-public organizations and 44% of private organizations did not provide education and training in safety management (p<0.001, according to establishment). (author)

  4. Predicting psychopharmacological drug effects on actual driving performance (SDLP) from psychometric tests measuring driving-related skills.

    Science.gov (United States)

    Verster, Joris C; Roth, Thomas

    2012-03-01

    There are various methods to examine driving ability. Comparisons between these methods and their relationship with actual on-road driving is often not determined. The objective of this study was to determine whether laboratory tests measuring driving-related skills could adequately predict on-the-road driving performance during normal traffic. Ninety-six healthy volunteers performed a standardized on-the-road driving test. Subjects were instructed to drive with a constant speed and steady lateral position within the right traffic lane. Standard deviation of lateral position (SDLP), i.e., the weaving of the car, was determined. The subjects also performed a psychometric test battery including the DSST, Sternberg memory scanning test, a tracking test, and a divided attention test. Difference scores from placebo for parameters of the psychometric tests and SDLP were computed and correlated with each other. A stepwise linear regression analysis determined the predictive validity of the laboratory test battery to SDLP. Stepwise regression analyses revealed that the combination of five parameters, hard tracking, tracking and reaction time of the divided attention test, and reaction time and percentage of errors of the Sternberg memory scanning test, together had a predictive validity of 33.4%. The psychometric tests in this test battery showed insufficient predictive validity to replace the on-the-road driving test during normal traffic.

  5. Technical difficulties and challenges for performing safety analysis on digital I and C systems

    International Nuclear Information System (INIS)

    Yih, Swu

    1996-01-01

    Performing safety analysis on digital I and C systems is an important task for nuclear safety analysts. The analysis results can not only confirm that the system is well-developed but also provide crucial evidence for licensing process. However, currently both I and C developers and regulators have difficulties in evaluating the safety of digital I and C systems. To investigate this problem, this paper propose a frame-based model to analyze the working and failure mechanisms of software and its interaction with the environment. Valid isomorphic relationship between the logical (software) and the physical (hardware environment) frame is identified as a major factor that determines the safe behavior of the software. The failures that may potentially cause the violation of isomorphic relations are also discussed. To perform safety analysis on digital I and C systems, analysts need to predict the effects incurred by such failures. However, due to lack of continuity, regularity, integrity, and high complexity of software structure, software does not have a stable and predictable pattern of behavior, which in turn makes the trustworthiness of results of software safety analysis susceptible. Our model can explain many troublesome events experienced by computer controlled systems. Implications and possible directions for improvement are also discussed. (author)

  6. Precise and accurate train run data: Approximation of actual arrival and departure times

    DEFF Research Database (Denmark)

    Richter, Troels; Landex, Alex; Andersen, Jonas Lohmann Elkjær

    with the approximated actual arrival and departure times. As a result, all future statistics can now either be based on track circuit data with high precision or approximated actual arrival times with a high accuracy. Consequently, performance analysis will be more accurate, punctuality statistics more correct, KPI...

  7. Preliminary Performance Analysis Program Development for Safety System with Safeguard Vessel

    International Nuclear Information System (INIS)

    Kang, Han-Ok; Lee, Jun; Park, Cheon-Tae; Yoon, Ju-Hyeon; Park, Keun-Bae

    2007-01-01

    SMART is an advanced modular integral type pressurized water reactor for a seawater desalination and an electricity production. Major components of the reactor coolant system such as the pressurizer, Reactor Coolant Pump (RCP), and steam generators are located inside the reactor vessel. The SMART can fundamentally eliminate the possibility of large break loss of coolant accidents (LBLOCAs), improve the natural circulation capability, and better accommodate and thus enhance a resistance to a wide range of transients and accidents. The safety goals of the SMART are enhanced through highly reliable safety systems such as the passive residual heat removal system (PRHRS) and the safeguard vessel coupled with the passive safety injection feature. The safeguard vessel is a steel-made, leak-tight pressure vessel housing the RPV, SIT, and the associated valves and pipelines. A primary function of the safeguard vessel is to confine any radioactive release from the primary circuit within the vessel under DBAs related to loss of the integrity of the primary system. A preliminary performance analysis program for a safety system using the safeguard vessel is developed in this study. The developed program is composed of several subroutines for the reactor coolant system, passive safety injection system, safeguard vessel including the pressure suppression pool, and PRHRS. A small break loss of coolant accident at the upper part of a reactor is analyzed and the results are discussed

  8. Perceived Motor Competence Differs From Actual Performance in 8-Year-Old Neonatal ECMO Survivors

    NARCIS (Netherlands)

    Toussaint, L.C.; Cammen-van Zijp, M.H. van der; Janssen, A.J.; Tibboel, D.; Heijst, A.F. van; Ijsselstijn, H.

    2016-01-01

    OBJECTIVE: To assess perceived motor competence, social competence, self-worth, health-related quality of life, and actual motor performancein 8-year-old survivors of neonatal extracorporeal membrane oxygenation (ECMO). METHODS: In a prospective nationwide study, 135 children completed the extended

  9. Organizational safety climate and supervisor safety enforcement: Multilevel explorations of the causes of accident underreporting.

    Science.gov (United States)

    Probst, Tahira M

    2015-11-01

    According to national surveillance statistics, over 3 million employees are injured each year; yet, research indicates that these may be substantial underestimates of the true prevalence. The purpose of the current project was to empirically test the hypothesis that organizational safety climate and transactional supervisor safety leadership would predict the extent to which accidents go unreported by employees. Using hierarchical linear modeling and survey data collected from 1,238 employees in 33 organizations, employee-level supervisor safety enforcement behaviors (and to a less consistent extent, organizational-level safety climate) predicted employee accident underreporting. There was also a significant cross-level interaction, such that the effect of supervisor enforcement on underreporting was attenuated in organizations with a positive safety climate. These results may benefit human resources and safety professionals by pinpointing methods of increasing the accuracy of accident reporting, reducing actual safety incidents, and reducing the costs to individuals and organizations that result from underreporting. (c) 2015 APA, all rights reserved).

  10. Physician job satisfaction related to actual and preferred job size.

    Science.gov (United States)

    Schmit Jongbloed, Lodewijk J; Cohen-Schotanus, Janke; Borleffs, Jan C C; Stewart, Roy E; Schönrock-Adema, Johanna

    2017-05-11

    Job satisfaction is essential for physicians' well-being and patient care. The work ethic of long days and hard work that has been advocated for decades is acknowledged as a threat for physicians' job satisfaction, well-being, and patient safety. Our aim was to determine the actual and preferred job size of physicians and to investigate how these and the differences between them influence physicians' job satisfaction. Data were retrieved from a larger, longitudinal study among physicians starting medical training at Groningen University in 1982/83/92/93 (N = 597). Data from 506 participants (85%) were available for this study. We used regression analysis to investigate the influence of job size on physicians' job satisfaction (13 aspects) and ANOVA to examine differences in job satisfaction between physicians wishing to retain, reduce or increase job size. The majority of the respondents (57%) had an actual job size less than 1.0 FTE. More than 80% of all respondents preferred not to work full-time in the future. Respondents' average actual and preferred job sizes were .85 FTE and .81 FTE, respectively. On average, respondents who wished to work less (35% of respondents) preferred a job size reduction of 0.18 FTE and those who wished to work more (12%) preferred an increase in job size of 0.16 FTE. Job size influenced satisfaction with balance work-private hours most (β = -.351). Physicians who preferred larger job sizes were - compared to the other groups of physicians - least satisfied with professional accomplishments. A considerable group of physicians reported a gap between actual and preferred job size. Realizing physicians' preferences as to job size will hardly affect total workforce, but may greatly benefit individual physicians as well as their patients and society. Therefore, it seems time for a shift in work ethic.

  11. Improved nuclear power plant operations through performance-based safety regulation

    International Nuclear Information System (INIS)

    Golay, M.W.

    1998-01-01

    The US Nuclear Regulatory Commission (NRC) has recently instituted use of Risk-Informed, Performance-Based Regulation (RIPBR) for protecting public safety in the use of nuclear power. This was done most importantly during June 1997 in issuance of revised Regulatory Guides and Standard Review Plan (SRP) guidance to licensees and the NRC staff. The propose of RIPBR is to replace the previously-used system of prescriptive regulation, which focuses upon what licensees must do, to a system which focuses upon what they must achieve. RIPBR is goals-oriented and the previous system is means-oriented. This regulatory change is potentially revolutionary, and offers many opportunities for improving the efficiency of improving both nuclear power operations and safety. However, it must be nurtured carefully if is to be successful. The work reported in this paper is concerned with showing how RIPBR can be implemented successfully, with benefits in both areas being attained. It is also concerned with how several of the practical barriers to establishing a workable new regulatory system can be overcome. This work, sponsored by the US Dept. of Energy, is being performed in collaboration with Northeast Utilities Services Crop. and the Idaho National Engineering Laboratory. In our work we have examined a practical safety-related example at the Millstone 3 nuclear power station for implementation of RIPBR. In this examination we have formulated a set of modifications to the plant's technical specifications, and are in the process of investigating their bases and refining the modifications. (author)

  12. Exploiting data from safety investigations and processes to assess performance of safety management aspects

    NARCIS (Netherlands)

    Karanikas, Nektarios

    2016-01-01

    This paper presents an alternative way to use records from safety investigations as a means to support the evaluation of safety management (SM) aspects. Datasets from safety investigation reports and progress records of an aviation organization were analyzed with the scope of assessing safety

  13. Cognitive human reliability analysis for an assessment of the safety significance of complex transients

    International Nuclear Information System (INIS)

    Amico, P.J.; Hsu, C.J.; Youngblood, R.W.; Fitzpatrick, R.G.

    1989-01-01

    This paper reports that as part of a probabilistic assessment of the safety significance of complex transients at certain PWR power plants, it was necessary to perform a cognitive human reliability analysis. To increase the confidence in the results, it was desirable to make use of actual observations of operator response which were available for the assessment. An approach was developed which incorporated these observations into the human cognitive reliability (HCR) modeling approach. The results obtained provided additional insights over what would have been found using other approaches. These insights were supported by the observations, and it is suggested that this approach be considered for use in future probabilistic safety assessments

  14. Recent Trends In The Methods Of Safety Assessment Of Rad Waste Treatment And Disposal

    International Nuclear Information System (INIS)

    Mahmoud, N.S.

    2012-01-01

    Radioactive waste management system involves a huge variety of processes and activities. This includes; collection and segregation, pretreatment, treatment, conditioning, storage and finally disposal. To assure the safety of the different facility of each step in the waste management system, the operator should prepare a safety analysis report to be assessed by the national regulatory body. The content of the safety analysis report must include all data about the site, facility design, operational phase, waste materials, and safety assessment methodologies. Safety assessment methodologies are iterative processes involving site-specific, prospective modeling evaluations of the pre-operational, operational, and post-closure time in case of disposal facilities. The safety assessment focuses primarily on a decision about compliance with performance objectives, rather than the much more difficult problem of predicting actual radiological impacts on the public at far future times. The recent organization processes of the safety assessment are improved by the ISAM working group from IAEA for waste disposal site. These safety assessment methodologies have been modified within SADRWMS IAEA project for the establishment of safety methodologies for the pre-disposal facilities (treatment and storage facilities) and the disposal site.

  15. Exploration of nuclear power enterprise 'STAR' management performance evaluation system

    International Nuclear Information System (INIS)

    Wang Sen

    2005-01-01

    From the angle of nuclear power enterprise safety culture, this essay breaks the connotations of the safety culture down to nine aspects (target management, safety management, quality management, housekeeping, cost control, authorization management, teamwork, communication and continued improvement), with each aspect divided into five levels of star class according to its own characteristics. A comparison is made between the actualities of the enterprise and star management performance evaluation system to find out the gap and identify ways of continued improvement to elevate the enterprise management level, thereby developing a standard system of conducting qualitative and quantitative evaluation to the management process. Apart from its evaluation function, this system provides a guideline on the work orientation, method, and steps to elevate work level and capability for the managers performing specific management actions. It is also a system of measuring and evaluating the executive force of the company's management and its employees. (author)

  16. Exposure data and risk indicators for safety performance assessment in Europe.

    NARCIS (Netherlands)

    Papadimitriou, E. Yannis, G. Bijleveld, F.D. & Cardoso, J.L.

    2013-01-01

    The objective of this paper is the analysis of the state-of-the-art in risk indicators and exposure data for safety performance assessment in Europe, in terms of data availability, collection methodologies and use. More specifically, the concepts of exposure and risk are explored, as well as the

  17. The consideration of ecological safety in judicial practice-also on the ecological safety legislation

    Institute of Scientific and Technical Information of China (English)

    L(U) Zhongmei

    2006-01-01

    Ecological safety has been one of the hot issues of environmental law in recent years.The maintenance of ecological safety has become one of the legislative principles,as exemplified by the revision of the Law of Sand Prevention and Sand.Management and the Law against Solid Waste Environmental Pollution,and the relevant rules that will be established.However actual cases will still happen,whether the legislators have made the statutory law or not.While scholars and legislators are debating,the judges have to handle cases and render judgments.Through the analysis of a case,this article will discuss the feasibility for judges to make ecological safety considerations in the judicial process by applying the principle of good faith and will also discuss the legislative issues related to ecological safety.

  18. Integrating safety and health during deactiviation: With lessons learned from PUREX

    International Nuclear Information System (INIS)

    1995-01-01

    This report summarizes an integrated safety and health approach used during facility deactivation activities at the Department of Energy (DOE) Plutonium-Uranium Extraction (PUREX) Facility in Hanford, Washington. Resulting safety and health improvements and the potential, complex-wide application of this approach are discussed in this report through a description of its components and the impacts, or lessons-learned, of its use during the PUREX deactivation project. As a means of developing and implementing the integrated safety and health approach, the PUREX technical partnership was established in 1993 among the Office of Environment, Safety and Health's Office of Worker Health and Safety (EH-5); the Office of Environmental Management's Offices of Nuclear Material and Facility Stabilization (EM-60) and Compliance and Program Coordination (EM-20); the DOE Richland Operations Office; and the Westinghouse Hanford Company. It is believed that this report will provide guidance for instituting an integrated safety and health approach not only for deactivation activities, but for decommissioning and other clean-up activities as well. This confidence is based largely upon the rationality of the approach, often termed as common sense, and the measurable safety and health and project performance results that application of the approach produced during actual deactivation work at the PUREX Facility

  19. Long term safety requirements and safety indicators for the assessment of underground radioactive waste repositories

    International Nuclear Information System (INIS)

    Vovk, Ivan

    1998-01-01

    This presentation defines: waste disposal, safety issues, risk estimation; describes the integrated waste disposal process including quality assurance program. Related to actinides inventory it shows the main results of calculated activity obtained by deterministic estimation. It includes the Radioactive Waste Safety Standards and requirements; features related to site, design and waste package characteristics, as technical long term safety criteria for radioactive waste disposal facilities. Fundamental concern regarding the safety of radioactive waste disposal systems is their radiological impact on human beings and the environment. Safety requirements and criteria for judging the level of safety of such systems have been developed and there is a consensus among the international community on their basis within the well-established system of radiological protection. So far, however, little experience has been gained in applying long term safety criteria to actual disposal systems; consequently, there is an international debate on the most appropriate nature and form of the criteria to be used, taking into account the uncertainties involved. Emerging from the debate is the increasing conviction that the combined use of a variety of indicators would be advantageous in addressing the issue of reasonable assurance in the different time frames involved and in supporting the safety case for any particular repository concept. Indicators including risk, dose, radionuclide concentration, transit time, toxicity indices, fluxes at different points within the system, and barrier performance have all been identified as potentially relevant. Dose and risk are the indicators generally seen as most fundamental, as they seek directly to describe the radiological impact of a disposal system, and these are the ones that have been incorporated into most national standards to date. There are, however, certain problems in applying them. Application of a variety of different indicators

  20. GT-MHR design, performance, and safety

    International Nuclear Information System (INIS)

    Neylan, A.J.; Shenoy, A.; Silady, F.A.; Dunn, T.D.

    1994-11-01

    The Gas Turbine-Modular Helium Reactor (GT-MHR) is the result of coupling the evolution of a low power density passively safe modular reactor with key technology developments in the U.S. during the last decade: large industrial gas turbines; large active magnetic bearings; and compact, highly effective plate-fin heat exchangers. This is accomplished through the unique use of the Brayton cycle to produce electricity with the helium as primary coolant from the reactor directly driving the gas turbine electrical generator. This cycle can achieve a high net efficiency in the range of 45% to 48%. In the design of the GT-MHR the desirable inherent characteristics of the inert helium coolant, graphite core, and the coated fuel particles are supplemented with specific design features such as passive heat removal to achieve the safety objective of not disturbing the normal day-to-day activities of the public even for beyond design basis rare accidents. Each GT-MHR plant consists of four modules. The GT-MHR module components are contained within steel pressure vessels: a reactor vessel, a power conversion vessel, and a connecting cross vessel. All vessels are sited underground in a concrete silo, which serves as an independent vented low pressure containment structure. By capitalizing on industrial and aerospace gas turbine development, highly effective heat exchanger designs, and inherent gas cooled reactor temperature characteristics, the passively safe GT-MHR provides a sound technical, monetary, and environmental basis for new nuclear power generating capacity. This paper provides an update on the status of the design, which has been under development on the US-DOE program since February 1993. An assessment of plant performance and safety is also included

  1. Simulation for Prediction of Entry Article Demise (SPEAD): An Analysis Tool for Spacecraft Safety Analysis and Ascent/Reentry Risk Assessment

    Science.gov (United States)

    Ling, Lisa

    2014-01-01

    For the purpose of performing safety analysis and risk assessment for a potential off-nominal atmospheric reentry resulting in vehicle breakup, a synthesis of trajectory propagation coupled with thermal analysis and the evaluation of node failure is required to predict the sequence of events, the timeline, and the progressive demise of spacecraft components. To provide this capability, the Simulation for Prediction of Entry Article Demise (SPEAD) analysis tool was developed. The software and methodology have been validated against actual flights, telemetry data, and validated software, and safety/risk analyses were performed for various programs using SPEAD. This report discusses the capabilities, modeling, validation, and application of the SPEAD analysis tool.

  2. Exploring the state of health and safety management system performance measurement in mining organizations.

    Science.gov (United States)

    Haas, Emily Joy; Yorio, Patrick

    2016-03-01

    Complex arguments continue to be articulated regarding the theoretical foundation of health and safety management system (HSMS) performance measurement. The culmination of these efforts has begun to enhance a collective understanding. Despite this enhanced theoretical understanding, however, there are still continuing debates and little consensus. The goal of the current research effort was to empirically explore common methods to HSMS performance measurement in mining organizations. The purpose was to determine if value and insight could be added into the ongoing approaches of the best ways to engage in health and safety performance measurement. Nine site-level health and safety management professionals were provided with 133 practices corresponding to 20 HSMS elements, each fitting into the plan, do, check, act phases common to most HSMS. Participants were asked to supply detailed information as to how they (1) assess the performance of each practice in their organization, or (2) would assess each practice if it were an identified strategic imperative. Qualitative content analysis indicated that the approximately 1200 responses provided could be described and categorized into interventions , organizational performance , and worker performance . A discussion of how these categories relate to existing indicator frameworks is provided. The analysis also revealed divergence in two important measurement issues; (1) quantitative vs qualitative measurement and reporting; and (2) the primary use of objective or subjective metrics. In lieu of these findings we ultimately recommend a balanced measurement and reporting approach within the three metric categories and conclude with suggestions for future research.

  3. Techno-economic analysis of a 2.1 kW rooftop photovoltaic-grid-tied system based on actual performance

    International Nuclear Information System (INIS)

    Adaramola, Muyiwa S.

    2015-01-01

    Highlights: • The economic analysis of rooftop PV grid-tied installation is examined. • Based on actual performance, the LCOE of the system is estimated as US$0.246/kW h. • Feed-in-tariff of US$0.356/kW h is estimated with no financial support. • To encourage installation of PV system, financial support of up to 40% of the investment is suggested. - Abstract: As more attention is being focus on the development of renewable energy resources globally, technical and economic assessments of these resources are crucial to ascertain their viability. These assessments can be more meaningful, if they are based on field and actual performance of the renewable energy conversion systems. This study presents the economic analysis of a rooftop 2.07 kW grid-connected photovoltaic energy system installation located in Ås (59.65°N and longitude 10.76°E, and about 105 m above sea level), Norway. Both the annual and monthly costs of energy produced by the system are determined. In addition, the feed-in tariff that can give internal rate of return of about 7.5% on investment on this installation was examined. Based on assumptions used in this study, feed-in-tariff of US$0.356/kW h is estimated for a project with economic life of 25 years with no other financial support. This translates to US$0.110/kW h premium over the levelized cost of energy of US$0.246/kW h generated by the system. However, if the financial support is more than 45% of the initial investment cost, no further premium fee is necessary to support this type of system

  4. Safety performance assessment of food industry facilities using a fuzzy approach

    Directory of Open Access Journals (Sweden)

    F. Barreca

    2013-09-01

    Full Text Available The latest EU policies focus on the issue of food safety with a view to assuring adequate and standard quality levels for the food produced and/or consumed within the EC. To that purpose, the environment where agricultural products are manufactured and processed plays a crucial role in achieving food hygiene. As a consequence, it is of the utmost importance to adopt proper building solutions which meet health and hygiene requirements and to use suitable tools to measure the levels achieved. Similarly, it is necessary to verify and evaluate the level of safety and welfare of the workers in their working environment. The safety of the workers has not only an ethical and social value but also an economic implication, since possible accidents or environmental stressors are the major causes of the lower efficiency and productivity of workers. However, the technical solutions adopted in the manufacturing facilities in order to achieve adequate levels of safety and welfare of the workers are not always consistent with the solutions aimed at achieving adequate levels of food hygiene, even if both of them comply with sectoral rules which are often unconnected with each other. Therefore, it is fundamental to design suitable models of analysis that allow assessing buildings as a whole, taking into account both health and hygiene safety as well as the safety and welfare of workers. Hence, this paper proposes an evaluation model that, based on an established study protocol and on the application of a fuzzy logic procedure, allows evaluating the global safety level of a building. The proposed model allows to obtain a synthetic and global value of the building performance in terms of food hygiene and safety and welfare of the workers as well as to highlight possible weaknesses. Though the model may be applied in either the design or the operational phase of a building, this paper focuses on its application to certain buildings already operational in a specific

  5. Safety parameter display systems' effect on operator performance

    International Nuclear Information System (INIS)

    Cerven, F.; Ford, R.E.; Blackman, H.S.

    1983-01-01

    Computer generated displays are a powerful and flexible tool for presenting data to the operators of nuclear power plants. Such displays are currently being developed in industry for use as safety parameter displays and for use in advanced control rooms. There exists a need for methods to objectively evaluate the effect of these displays, positive or negative, on the performance of control room personnel. Results of developing one such method, noninteractive simulation, and the two experiments that were performed to determine if it can be used as a method for evaluating computer displays are presented. This method is more objective and powerful than pencil and paper methods because it measures human performance rather than opinion or perference, has excellent control of the experimental variables, and has a higher fidelity to the control room environment. The results of these experiments indicates that the present methodology does not differentiate among the display types tested at a statistically significant level. In other words, all display types tested worked equally well in providing operators needed information

  6. A false sense of security: safety behaviors erode objective speech performance in individuals with social anxiety disorder.

    Science.gov (United States)

    Rowa, Karen; Paulitzki, Jeffrey R; Ierullo, Maria D; Chiang, Brenda; Antony, Martin M; McCabe, Randi E; Moscovitch, David A

    2015-05-01

    In the current study, 55 participants with a diagnosis of generalized social anxiety disorder (SAD), 23 participants with a diagnosis of an anxiety disorder other than SAD with no comorbid SAD, and 50 healthy controls completed a speech task as well as self-reported measures of safety behavior use. Speeches were videotaped and coded for global and specific indicators of performance by two raters who were blind to participants' diagnostic status. Results suggested that the objective performance of people with SAD was poorer than that of both control groups, who did not differ from each other. Moreover, self-reported use of safety behaviors during the speech strongly mediated the relationship between diagnostic group and observers' performance ratings. These results are consistent with contemporary cognitive-behavioral and interpersonal models of SAD and suggest that socially anxious individuals' performance skills may be undermined by the use of safety behaviors. These data provide further support for recommendations from previous studies that the elimination of safety behaviors ought to be a priority in cognitive behavioral therapy for SAD. Copyright © 2014. Published by Elsevier Ltd.

  7. 49 CFR 385.337 - What happens if a new entrant refuses to permit a safety audit to be performed on its operations?

    Science.gov (United States)

    2010-10-01

    ... safety audit to be performed on its operations? 385.337 Section 385.337 Transportation Other Regulations... TRANSPORTATION FEDERAL MOTOR CARRIER SAFETY REGULATIONS SAFETY FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.337 What happens if a new entrant refuses to permit a safety audit to be performed on its...

  8. Nuclear power performance and safety. V.6.: Indexes and lists

    International Nuclear Information System (INIS)

    1988-01-01

    The sixth volume of the proceedings of the international conference on nuclear power performance and safety organized by the IAEA and held in Vienna between 28 September and 2 October 1987 presents the contents of volumes 1-5, the list of Chairmen of Sessions and the Secretariat of the Conference, the list of participants, the author and transliteration indexes, the index of papers and posters by number

  9. Experience of RIA safety analyses performance for NPP Temelin core arranged with TVSA-T fuel assemblies

    International Nuclear Information System (INIS)

    Kryukov, S.A.; Lizorkin, M.P.

    2010-01-01

    The contents of the presentation are as follows: 1. Definition of categories for initiating events; 2. Acceptance criteria for safety assessment; 3. Main aspects of safety assessment methodology; 4. Main stages of calculation analysis; 5. Interface with other parts of the core design; 6. Codes used for calculation; 6.1 Main performances of code package TIGR-1; 6.2 Main performances of code BIPR-7A; 7. TIGR-1 accounting of design margins in calculation of fuel rod powers; 8. Peculiar features of Instrumentation and Control System for Temelin NPP; 9. Calculations; 10. Checklist of margin data important for reload safety assessment. (P.A.)

  10. Electronic isolators used in safety systems of US nuclear power plants

    International Nuclear Information System (INIS)

    Nielsen, J.R.

    1986-01-01

    An evaluation program has been conducted for electronic isolators used in safety systems of US nuclear power plants. As a result of the program, some recommendations are made for test methods that can be used to ensure that isolation devices are being qualified adequately to satisfy IEEE-279 requirements. These recommendations are based on studies made on National Standards; conversations held with utility personnel, Nuclear Steam System Suppliers, Architect Engineers, and the isolator vendor staff; and analysis of actual tests performed on sample isolators

  11. Calculation of the actual cost in the chemical fertilizer industry

    Directory of Open Access Journals (Sweden)

    Ion Ionescu

    2017-12-01

    Full Text Available The main goal of the research is to present a way of organising the managerial accounting of totally and semi finished product obtained in chemical fertilizer industry entities. For this study, we analyzed the current principle of managerial accounting to an entity in the studied area, in order to emphasize the need of organizing and implementing a modern accounting management to control the cost and increase the performance of the entities in this area, starting from the premise that there are sufficient similarities between entities in the field. The research has highlighted the fact that, nowadays, the cost calculation is organized using traditional methods, which focus on the monthly determination of the actual unit cost per product (semi-fabric and that it is necessary to organize and implement a managerial accounting, based on the use of a modern method, namely the standard cost method combined with cost centre method. The major implications of the proposed system for the researched field are the monthly calculation of actual costs per cost centres, the calculation of the actual cost per product, as the final cost carrier, to be performed over longer periods of time, usually, quarterly.

  12. Schoolbus driver performance can be improved with driver training, safety incentivisation, and vehicle roadworthy modifications

    Directory of Open Access Journals (Sweden)

    A van Niekerk

    2017-03-01

    Full Text Available In South Africa (SA, the school transport industry provides millions of children with a means of travelling to and from school. The industry has, however, been reported to be plagued by widespread safety concerns. The consequent road traffic incidents have often been attributed to driver factors, including driving in excess of legal speeds or at inappropriate speeds; driving while under the influence of alcohol, while sleepy or fatigued; or driving without using protective equipment for vehicle occupants. There are currently very few SA interventions that specifically target this important industry role-player. The Safe Travel to School Programme was recently implemented by a national child safety agency, with a focus on driver road safety awareness, defensive driver training, eye- testing, vehicle roadworthy inspections with selected upgrades, incentives for safe performance, and implementation of a vehicle telematics tracking system with regular, individual driving behaviour information updates. This quasi-experimental study offers an evaluation of the initial impact on safety performance of this telematics-based driver and vehicle safety intervention in terms of speeding, acceleration, braking, cornering, and time-of-day driving, and compares the school transport driver performance with that of general motorists. Despite concerns that some school transport vehicles are used for multiple purposes outside of school transport duties, at night, and for longer distances, overall these vehicles recorded lower percentages of speeding, lower harsh braking, and lower average harsh cornering and acceleration than general drivers.

  13. Combined leadless pacemaker and subcutaneous implantable defibrillator therapy: feasibility, safety, and performance

    NARCIS (Netherlands)

    Tjong, F. V. Y.; Brouwer, T. F.; Smeding, L.; Kooiman, K. M.; de Groot, J. R.; Ligon, D.; Sanghera, R.; Schalij, M. J.; Wilde, A. A. M.; Knops, R. E.

    2016-01-01

    The subcutaneous implantable cardioverter-defibrillator (S-ICD) and leadless pacemaker (LP) are evolving technologies that do not require intracardiac leads. However, interactions between these two devices are unexplored. We investigated the feasibility, safety, and performance of combined LP and

  14. Safety Specialist Manpower, Manpower Resources. Volumes II and III.

    Science.gov (United States)

    Booz Allen and Hamilton, Inc., Washington, DC.

    These second and third volumes of a four-volume study of manpower in state highway safety programs over the next decade estimate manpower resources by state and in national aggregate and describe present and planned training programs for safety specialists. For each educational level, both total manpower and manpower actually available for…

  15. Safety and performance of a long life lithium-thionyl chloride battery

    Science.gov (United States)

    Cieslak, W. R.; Street, H. K.

    A Li/SOCl2 'D' cell for applications requiring 10 to 15 years life at very low drain rates, typically less than 150 microA, were developed. Maximizing cell safety and reliability, while delivering very good energy density, were the goals. These goals were achieved by designing the cell to be application specific. The low-rate cell was optimized to deliver up to 16 Ah at drain rates of less than 70 mA. By virtue of its low surface area, 145 cm(sup 2), the cell demonstrated excellent safety behavior. Safety testing was performed on individual cells as well as on two-cell and four-cell batteries. Single cells did not vent when short-circuited. Benign venting in a two cell string was produced, but only when the string was partially discharged before shorting. The vent mechanism is a 300 psi rupture pressure burst disc manufactured by BS&B Safety Systems. Benign venting is defined as full opening of the 3/8 in. dia vent hole without deformation of the case. Material is expelled from the cell without flame, and the cell stack remains largely intact. Venting of the Sandia-designed low rate cell was not produced under any other abuse test conditions. The vent functions as an ultimate safety mechanism in the case of severe abuse, but resistance to venting under normal use and mild abuse conditions is key to the achievement of high reliability.

  16. Safety measures for integrity test apparatus for IS process. Sulfuric acid decomposition section

    International Nuclear Information System (INIS)

    Noguchi, Hiroki; Kubo, Shinji; Iwatsuki, Jin; Onuki, Kaoru

    2013-07-01

    Hazardous substances such as sulfuric acid, sulfur dioxide and hydrogen iodide acid are employed in thermochemical Iodine-Sulfur (IS) process. It is necessary to take safety measure against workers and external environments to study experimentally on IS process. Presently we have been conducting to verify the soundness of main components made of engineering material in actual corrosive condition. An integrity test apparatus for the components of sulfuric acid decomposition was set up. We will use the hazardous substances such as sulfuric acid and sulfur dioxide and perform the experiment in pressurized condition in this integrity test. Safety measures for the test apparatus, operation and abnormal situation were considered prior to starting the test. This report summarized the consideration results for the safety measures on the integrity test apparatus for the components of sulfuric acid decomposition. (author)

  17. Correspondence between Simulator and On-Road Drive Performance: Implications for Assessment of Driving Safety.

    Science.gov (United States)

    Aksan, Nazan; Hacker, Sarah D; Sager, Lauren; Dawson, Jeffrey; Anderson, Steven; Rizzo, Matthew

    2016-03-01

    Forty-two younger (Mean age = 35) and 37 older drivers (Mean age = 77) completed four similar simulated drives. In addition, 32 younger and 30 older drivers completed a standard on-road drive in an instrumented vehicle. Performance in the simulated drives was evaluated using both electronic drive data and video-review of errors. Safety errors during the on-road drive were evaluated by a certified driving instructor blind to simulator performance, using state Department of Transportation criteria. We examined the degree of convergence in performance across the two platforms on various driving tasks including lane change, lane keeping, speed control, stopping, turns, and overall performance. Differences based on age group indicated a pattern of strong relative validity for simulator measures. However, relative rank-order in specific metrics of performance suggested a pattern of moderate relative validity. The findings have implications for the use of simulators in assessments of driving safety as well as its use in training and/or rehabilitation settings.

  18. Impact of Performance Obstacles on Intensive Care Nurses‘ Workload, Perceived Quality and Safety of Care, and Quality of Working Life

    Science.gov (United States)

    Gurses, Ayse P; Carayon, Pascale; Wall, Melanie

    2009-01-01

    Objectives To study the impact of performance obstacles on intensive care nurses‘ workload, quality and safety of care, and quality of working life (QWL). Performance obstacles are factors that hinder nurses‘ capacity to perform their job and that are closely associated with their immediate work system. Data Sources/Study Setting Data were collected from 265 nurses in 17 intensive care units (ICUs) between February and August 2004 via a structured questionnaire, yielding a response rate of 80 percent. Study Design A cross-sectional study design was used. Data were analyzed by correlation analyses and structural equation modeling. Principal Findings Performance obstacles were found to affect perceived quality and safety of care and QWL of ICU nurses. Workload mediated the impact of performance obstacles with the exception of equipment-related issues on perceived quality and safety of care as well as QWL. Conclusions Performance obstacles in ICUs are a major determinant of nursing workload, perceived quality and safety of care, and QWL. In general, performance obstacles increase nursing workload, which in turn negatively affect perceived quality and safety of care and QWL. Redesigning the ICU work system to reduce performance obstacles may improve nurses‘ work. PMID:19207589

  19. The roles of emotional intelligence, interpersonal skill, and transformational leadership on improving construction safety performance

    Directory of Open Access Journals (Sweden)

    Riza Yosia Sunindijo

    2013-09-01

    Full Text Available Due to the characteristics of the constructionindustry, human skills are essential for working with and through others inmanaging safety. Research has shown that emotional intelligence, interpersonalskill, and transformational leadership are human skill components that generatesuperior performance in today’s workplace. The aim of this research is toinvestigate the influence of project management personnel’s human skills on theimplementation of safety management tasks and development of safety climate inconstruction projects. The structural equation modelling (SEM method wasapplied to analyse the quantitative data collected and establishinterrelationship among the research variables. The results indicate thatemotional intelligence is a key factor for developing interpersonal skill andtransformational leadership, and for implementing safety management tasks whichleads to the development of safety climate. This research also found thatinterpersonal skill is needed for becoming transformational leaders whocontribute to the development of safety climate.

  20. Road safety issues for bus transport management.

    Science.gov (United States)

    Cafiso, Salvatore; Di Graziano, Alessandro; Pappalardo, Giuseppina

    2013-11-01

    Because of the low percentage of crashes involving buses and the assumption that public transport improves road safety by reducing vehicular traffic, public interest in bus safety is not as great as that in the safety of other types of vehicles. It is possible that less attention is paid to the significance of crashes involving buses because the safety level of bus systems is considered to be adequate. The purpose of this study was to evaluate the knowledge and perceptions of bus managers with respect to safety issues and the potential effectiveness of various technologies in achieving higher safety standards. Bus managers were asked to give their opinions on safety issues related to drivers (training, skills, performance evaluation and behaviour), vehicles (maintenance and advanced devices) and roads (road and traffic safety issues) in response to a research survey. Kendall's algorithm was used to evaluate the level of concordance. The results showed that the majority of the proposed items were considered to have great potential for improving bus safety. The data indicated that in the experience of the participants, passenger unloading and pedestrians crossing near bus stops are the most dangerous actions with respect to vulnerable users. The final results of the investigation showed that start inhibition, automatic door opening, and the materials and internal architecture of buses were considered the items most strongly related to bus passenger safety. Brake assistance and vehicle monitoring systems were also considered to be very effective. With the exception of driver assistance systems for passenger and pedestrian safety, the perceptions of the importance of other driver assistance systems for vehicle monitoring and bus safety were not unanimous among the bus company managers who participated in this survey. The study results showed that the introduction of new technologies is perceived as an important factor in improving bus safety, but a better understanding

  1. Prediction of Heat Transfer Performance on Horizontal U-Shaped Heat Exchanger in Passive Safety System Using MARS

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Seong-Su; Hong, Soon-Joon [FNC Tech, Yongin (Korea, Republic of); Cho, Hyoung-Kyu; Park, Goon-Cherl [Seoul National University, Seoul (Korea, Republic of)

    2015-10-15

    The design and the safety analysis of the passive safety systems are performed mainly using the best-estimate thermal-hydraulic analysis codes such as RELAP5 and MARS. This study developed the heat transfer model package for the horizontal U-shaped HX submerged in a pool by improving the horizontal in-tube condensation model and developing the outside-tube natural convective nucleate boiling model. This paper presents the HX model package and the validation results against the passive safety system-related experimental data of PASCAL and ATLAS-PAFS. This study developed the heat transfer model package of the horizontal U-shaped HX submerged in a pool in order to obtain a reliable prediction of the HX heat removal performance of the passive safety system, especially PAFS, using MARS. From the validation results, the proposed model package provided the improved prediction of HX performance (condensation, natural convective nucleate boiling, and heat removal rate of the HX) compared to the default model in MARS.

  2. Actualism and Fictional Characters

    Directory of Open Access Journals (Sweden)

    André Leclerc

    2016-04-01

    Full Text Available http://dx.doi.org/10.5007/1808-1711.2016v20n1p61 In what follows, I present only part of a program that consists in developing a version of actualism as an adequate framework for the metaphysics of intentionality. I will try to accommodate in that framework suggestions found in Kripke’s works and some positions developed by Amie Thomasson. What should we change if we accept “fictional entities” in the domain of the actual world? Actualism is the thesis that everything that exists belongs to the domain of the actual world and that there are no possibilia. I shall defend that there are abstract artefacts, like fictional characters, and institutions. My argument could be seen as a version of Moore’s paradox: it is paradoxical to say: “I made (created it, but I do not believe it exists”. Moreover, there are true sentences about them. I will examine what it means to include abstract artefacts in the domain of the actual world. I favour a use of “exist” that includes beings with no concrete occupation of tri-dimensional space; to exist, it is enough to have been introduced at some moment in history. Abstract artefacts, like fictional characters, exist in that sense. I argue that it is important to distinguish two perspectives (internal and external in order to clarify the kind of knowledge we have of fictional characters. However, their existence presupposes a relation of dependence to a material basis and the mental activities of many people.

  3. Impact of hospital security programmes and workplace aggression on nurse perceptions of safety.

    Science.gov (United States)

    Blando, James D; O'Hagan, Emily; Casteel, Carri; Nocera, Mary-Alice; Peek-Asa, Corinne

    2013-04-01

    To assess how nurses' perception of their safety and risk of violence was affected by their work environment and whether this perception correlated with their actual risk. The work environment has an impact on nurses' perception of their risk of violence and this perception affects worker productivity, quality, employee retention, worker satisfaction and their actual safety. A cross-sectional survey was conducted in person of 314 emergency department nurses and 143 psychiatric nurses, and assault data was collected from injury logs. This study found that nurses in the emergency and psychiatric units differed in their perception of violence and safety. The workplace elements that led to a perception of lower risk of violence were not correlated with a lower rate of injury from violent acts. The nurses' beliefs about the adequacy of security equipment, security guards and the frequency of verbal abuse were strongly correlated with perceived safety. Several factors that influence nurses' perception of their risk of violence are not well correlated with their actual risk. Managers must address workplace elements that affect nurse perceptions because this has an impact on quality and employee retention. They must also address factors that have an impact on the actual risk of violence because this study showed, for the first time, that these may differ from perceptions. © 2012 Blackwell Publishing Ltd.

  4. High-reliability emergency response teams in the hospital: improving quality and safety using in situ simulation training.

    Science.gov (United States)

    Wheeler, Derek S; Geis, Gary; Mack, Elizabeth H; LeMaster, Tom; Patterson, Mary D

    2013-06-01

    In situ simulation training is a team-based training technique conducted on actual patient care units using equipment and resources from that unit, and involving actual members of the healthcare team. We describe our experience with in situ simulation training in a major children's medical centre. In situ simulations were conducted using standardised scenarios approximately twice per month on inpatient hospital units on a rotating basis. Simulations were scheduled so that each unit participated in at least two in situ simulations per year. Simulations were conducted on a revolving schedule alternating on the day and night shifts and were unannounced. Scenarios were preselected to maximise the educational experience, and frequently involved clinical deterioration to cardiopulmonary arrest. We performed 64 of the scheduled 112 (57%) in situ simulations on all shifts and all units over 21 months. We identified 134 latent safety threats and knowledge gaps during these in situ simulations, which we categorised as medication, equipment, and/or resource/system threats. Identification of these errors resulted in modification of systems to reduce the risk of error. In situ simulations also provided a method to reinforce teamwork behaviours, such as the use of assertive statements, role clarity, performance of frequent updating, development of a shared mental model, performance of independent double checks of high-risk medicines, and overcoming authority gradients between team members. Participants stated that the training programme was effective and did not disrupt patient care. In situ simulations can identify latent safety threats, identify knowledge gaps, and reinforce teamwork behaviours when used as part of an organisation-wide safety programme.

  5. The actual development of European aviation safety requirements in aviation medicine: prospects of future EASA requirements.

    Science.gov (United States)

    Siedenburg, J

    2009-04-01

    Common Rules for Aviation Safety had been developed under the aegis of the Joint Aviation Authorities in the 1990s. In 2002 the Basic Regulation 1592/2002 was the founding document of a new entity, the European Aviation Safety Agency. Areas of activity were Certification and Maintenance of aircraft. On 18 March the new Basic Regulation 216/2008, repealing the original Basic Regulation was published and applicable from 08 April on. The included Essential Requirements extended the competencies of EASA inter alia to Pilot Licensing and Flight Operations. The future aeromedical requirements will be included as Annex II in another Implementing Regulation on Personnel Licensing. The detailed provisions will be published as guidance material. The proposals for these provisions have been published on 05 June 2008 as NPA 2008- 17c. After public consultation, processing of comments and final adoption the new proposals may be applicable form the second half of 2009 on. A transition period of four year will apply. Whereas the provisions are based on Joint Aviation Requirement-Flight Crew Licensing (JAR-FCL) 3, a new Light Aircraft Pilot Licence (LAPL) project and the details of the associated medical certification regarding general practitioners will be something new in aviation medicine. This paper consists of 6 sections. The introduction outlines the idea of international aviation safety. The second section describes the development of the Joint Aviation Authorities (JAA), the first step to common rules for aviation safety in Europe. The third section encompasses a major change as next step: the foundation of the European Aviation Safety Agency (EASA) and the development of its rules. In the following section provides an outline of the new medical requirements. Section five emphasizes the new concept of a Leisure Pilot Licence. The last section gives an outlook on ongoing rulemaking activities and the opportunities of the public to participate in them.

  6. An innovative fuel design concept for improved Light Water Reactor performance and safety

    International Nuclear Information System (INIS)

    Tulenko, J.S.; Connell, R.G.

    1993-01-01

    The primary goal of this research is to develop a new fuel design which will have improved thermal/mechanical performance characteristics greatly superior to current thermal and mechanical design performance. The mechanical/thermal constraints define the lifetime of the fuel, the maximum power at which the fuel can be operated, the probability of fuel failure over core lifetime, and the integrity of a core during a transient excursion. The thermal/mechanical limits act to degrade fuel integrity when they are violated. The purpose of this project is to investigate a novel design for light water reactor fuel which will extend fuel performance limits and improve reactor safety even further than is currently achieved. This project is investigating liquid metal bonding of LWR fuel in order to radically decrease fuel centerline temperatures which has major performance and safety benefits. The project will verify the compatibility of the liquid metal bond with both the fuel pellets and cladding material, verify the performance enhancement features of the new design over the fuel lifetime, and verify the economic fabricability of the concept and will show how this concept will benefit the LWR nuclear industry

  7. Recolecta: estado actual y perspectivas

    OpenAIRE

    López Medina, Alicia

    2010-01-01

    Estado actual del Recolector de ciencia abierta español: Recolecta y proyectos de futuro. López Medina, A. (2010). Recolecta: estado actual y perspectivas. X Workshop Rebiun sobre proyectos digitales. http://hdl.handle.net/10251/8710.

  8. Performance of safety management systems in Spanish food service establishments in view of their context characteristics

    NARCIS (Netherlands)

    Luning, P.A.; Chinchilla, A.C.; Jacxsens, L.; Kirezieva, K.K.; Rovira, J.

    2013-01-01

    Food service establishments (FSE) operate under restricted technological and organisational circumstances, making them susceptible to food safety problems as reported frequently. Aim of this study was to get insight in Food Safety Management System (FSMS) performance in different types of FSE in

  9. Requirements of actual final repository concepts for different host rock formations. Final report; Anforderungen an aktuelle Endlagerkonzepte fuer unterschiedliche Wirtsgesteinsformationen. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Fass, Thorsten; Hartwig-Thurat, Eva; Krischer, Angelika; Lambers, Ludger; Larue, Juergen; Uhlmann, Stephan; Weyand, Torben

    2017-08-15

    In the frame of the research project the basic requirements and technical safety specifications with respect to the retrievability of stored radioactive wastes for the different final repository concepts based on the host rock formations occurring in Germany are presented. Existing international disposal concepts for clay/claystone, granite and salt are described and compared to the actual German regulatory requirements. The safety engineering relations between stock piling and possible retrieval are described and evaluated.

  10. Nuclear power plant Isar. Actualized environmental statement 2012 on the consolidated environmental statement 2010

    International Nuclear Information System (INIS)

    2012-01-01

    The actualized environmental statement 2012 for the NPP Isar covers the following issues: Direct environmental aspects: heat dissipation to the environment, water management, radioactive matter release onto the environment, environmental monitoring, waste management, operational materials supply, radioactive materials transport, safety of the nuclear facilities, remote monitoring and information system, environmental protection, communication; indirect environmental aspects; core indicators according EMAS III, development of the environmental targets and programs, reference to the valid environmental regulations, declaration of the environmental consultant.

  11. Safety analysis report for packaging (onsite) transuranic performance demonstration program sample packaging

    International Nuclear Information System (INIS)

    Mccoy, J.C.

    1997-01-01

    The Transuranic Performance Demonstration Program (TPDP) sample packaging is used to transport highway route controlled quantities of weapons grade (WG) plutonium samples from the Plutonium Finishing Plant (PFP) to the Waste Receiving and Processing (WRAP) facility and back. The purpose of these shipments is to test the nondestructive assay equipment in the WRAP facility as part of the Nondestructive Waste Assay PDP. The PDP is part of the U. S. Department of Energy (DOE) National TRU Program managed by the U. S. Department of Energy, Carlsbad Area Office, Carlsbad, New Mexico. Details of this program are found in CAO-94-1045, Performance Demonstration Program Plan for Nondestructive Assay for the TRU Waste Characterization Program (CAO 1994); INEL-96/0129, Design of Benign Matrix Drums for the Non-Destructive Assay Performance Demonstration Program for the National TRU Program (INEL 1996a); and INEL-96/0245, Design of Phase 1 Radioactive Working Reference Materials for the Nondestructive Assay Performance Demonstration Program for the National TRU Program (INEL 1996b). Other program documentation is maintained by the national TRU program and each DOE site participating in the program. This safety analysis report for packaging (SARP) provides the analyses and evaluations necessary to demonstrate that the TRU PDP sample packaging meets the onsite transportation safety requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for an onsite Transportation Hazard Indicator (THI) 2 packaging. This SARP, however, does not include evaluation of any operations within the PFP or WRAP facilities, including handling, maintenance, storage, or operating requirements, except as they apply directly to transportation between the gate of PFP and the gate of the WRAP facility. All other activities are subject to the requirements of the facility safety analysis reports (FSAR) of the PFP or WRAP facility and requirements of the PDP

  12. Evaluation of the Quality of Occupational Health and Safety Management Systems Based on Key Performance Indicators in Certified Organizations.

    Science.gov (United States)

    Mohammadfam, Iraj; Kamalinia, Mojtaba; Momeni, Mansour; Golmohammadi, Rostam; Hamidi, Yadollah; Soltanian, Alireza

    2017-06-01

    Occupational Health and Safety Management Systems are becoming more widespread in organizations. Consequently, their effectiveness has become a core topic for researchers. This paper evaluates the performance of the Occupational Health and Safety Assessment Series 18001 specification in certified companies in Iran. The evaluation is based on a comparison of specific criteria and indictors related to occupational health and safety management practices in three certified and three noncertified companies. Findings indicate that the performance of certified companies with respect to occupational health and safety management practices is significantly better than that of noncertified companies. Occupational Health and Safety Assessment Series 18001-certified companies have a better level of occupational health and safety; this supports the argument that Occupational Health and Safety Management Systems play an important strategic role in health and safety in the workplace.

  13. Multiscale modeling and characterization for performance and safety of lithium-ion batteries

    International Nuclear Information System (INIS)

    Pannala, S.; Turner, J. A.; Allu, S.; Elwasif, W. R.; Kalnaus, S.; Simunovic, S.; Kumar, A.; Billings, J. J.; Wang, H.; Nanda, J.

    2015-01-01

    Lithium-ion batteries are highly complex electrochemical systems whose performance and safety are governed by coupled nonlinear electrochemical-electrical-thermal-mechanical processes over a range of spatiotemporal scales. Gaining an understanding of the role of these processes as well as development of predictive capabilities for design of better performing batteries requires synergy between theory, modeling, and simulation, and fundamental experimental work to support the models. This paper presents the overview of the work performed by the authors aligned with both experimental and computational efforts. In this paper, we describe a new, open source computational environment for battery simulations with an initial focus on lithium-ion systems but designed to support a variety of model types and formulations. This system has been used to create a three-dimensional cell and battery pack models that explicitly simulate all the battery components (current collectors, electrodes, and separator). The models are used to predict battery performance under normal operations and to study thermal and mechanical safety aspects under adverse conditions. This paper also provides an overview of the experimental techniques to obtain crucial validation data to benchmark the simulations at various scales for performance as well as abuse. We detail some initial validation using characterization experiments such as infrared and neutron imaging and micro-Raman mapping. In addition, we identify opportunities for future integration of theory, modeling, and experiments

  14. Lithium alloy-thionyl chloride cells - Performance and safety aspects

    Science.gov (United States)

    Peled, E.; Lombardi, A.; Schlaikjer, C. R.

    1983-06-01

    It is pointed out that the lithium-thionyl chloride cell has the highest energy density among all the commercially available batteries. The low rate, AA-bobbin cathode cell has been in the marketplace for several years, while the wound or spiral electrode cell is still in the stage of development. The main reason for this are safety problems. These problems are related to the very high reactivity of lithium toward thionyl chloride and the rather low melting point of lithium (180.5 C). The practical stability of the system depends on an LiCl-passivating layer which forms spontaneously on the immersion of the lithium in the electrolyte. This layer serves as a solid electrolyte interphase (SEI). Under certain extreme conditions, however, the SEI can be damaged in such a way that an explosion of the cell occurs. The present investigation is concerned with the reduction of the short-circuit current and the improvement of the safety performance of the cell by the use of special, treated lithium alloys.

  15. Safety and performance of a long life lithium-thionyl chloride battery

    Energy Technology Data Exchange (ETDEWEB)

    Cieslak, W.R.; Street, H.K.

    1992-12-31

    We have developed a Li/SOCl{sub 2} ``D`` cell for applications requiring 10 to 15 years life at very low drain rates, typically less than 150 {mu}A. Maximizing cell safety and reliability, while delivering very good energy density, have been the goals of our study. We have achieved these goals by designing the cell to be application specific. The low-rate cell has been optimized to deliver up to 16 Ah at drain rates of less than 70 mA. By virtue of its low surface area, 145 cm{sub 2}, the cell has demonstrated excellent safety behavior. Safety testing has been performed on individual cells as well as on two-cell and four-cell batteries. Single cells did not vent when short-circuited. We were able to produce benign venting in a two cell string, but only when the string was partially discharged before shorting. The vent mechanism is a 300 psi rupture pressure burst disc manufactured by BS&B Safety Systems. We define benign venting as full opening of the 3/8 in. dia vent hole without deformation of the case. Material is expelled from the cell without flame, and the cell stack remains largely intact. We have not produced venting of the Sandia-designed low rate cell under any other abuse test conditions. The vent functions as an ultimate safety mechanism in the case of severe abuse, but resistance to venting under normal use and mild abuse conditions is key to the achievement of high reliability.

  16. Safety and performance of a long life lithium-thionyl chloride battery

    Energy Technology Data Exchange (ETDEWEB)

    Cieslak, W.R.; Street, H.K.

    1992-01-01

    We have developed a Li/SOCl[sub 2] D'' cell for applications requiring 10 to 15 years life at very low drain rates, typically less than 150 [mu]A. Maximizing cell safety and reliability, while delivering very good energy density, have been the goals of our study. We have achieved these goals by designing the cell to be application specific. The low-rate cell has been optimized to deliver up to 16 Ah at drain rates of less than 70 mA. By virtue of its low surface area, 145 cm[sub 2], the cell has demonstrated excellent safety behavior. Safety testing has been performed on individual cells as well as on two-cell and four-cell batteries. Single cells did not vent when short-circuited. We were able to produce benign venting in a two cell string, but only when the string was partially discharged before shorting. The vent mechanism is a 300 psi rupture pressure burst disc manufactured by BS B Safety Systems. We define benign venting as full opening of the 3/8 in. dia vent hole without deformation of the case. Material is expelled from the cell without flame, and the cell stack remains largely intact. We have not produced venting of the Sandia-designed low rate cell under any other abuse test conditions. The vent functions as an ultimate safety mechanism in the case of severe abuse, but resistance to venting under normal use and mild abuse conditions is key to the achievement of high reliability.

  17. Road safety development in Europe: a decade of changes (2001-2010).

    Science.gov (United States)

    Shen, Yongjun; Hermans, Elke; Bao, Qiong; Brijs, Tom; Wets, Geert

    2013-11-01

    To evaluate the road safety development of a country over time, the percentage change in the number of road fatalities is traditionally the main indicator. However, simply considering the reduction in the road fatalities may not correctly reflect the real improvement in road safety because the transport circumstances of a country underlying the road fatalities also change every year. In this study, we present a new way for measuring the road safety performance change over time, which is to use the technique of data envelopment analysis (DEA) and the Malmquist productivity index. In doing so, we can not only focus on the evolution of road safety final outcomes within a given period, but also take the changes of different measures of exposure in the same period into account. In the application, the DEA-based Malmquist productivity index (DEA-MI) is used to measure the extent to which the EU countries have improved their road safety performance over the period 2001-2010. More objective and insightful results are obtained compared to the ones based on the traditional indicator. The results show considerable road safety progress in most of the Member States during these ten years, and the fatality risk rather than the fatality number on Europe's roads has actually been reduced by approximately half. However, the situation differed considerably from country to country. The decomposition of the DEA-MI into 'efficiency change' and 'technical change' further reveals that the bulk of the improvement during the last decade was attained through the adoption of productivity-enhancing new technologies throughout the road transport sector in Europe, rather than through the relatively underperforming countries catching up with those best-performing ones. Copyright © 2013 Elsevier Ltd. All rights reserved.

  18. Vibration of safety injection pump motors

    Energy Technology Data Exchange (ETDEWEB)

    Wattrelos, D.

    1996-12-01

    This paper covers a fault encountered in the safety injection pump motors of the French 900 MWe unit nuclear power stations. This fault was not revealed either during the low pressure safety injection and containment spray system pump qualification tests under accident conditions or during the special tests on a test bench carried out to attempt to replicate the fault and to identify ways of remedying it. This constitutes a potential common mode of failure of the safety injection system and the containment spray system pumps. The vibration phenomena illustrate the importance of carrying out tests in the plants under conditions as close as possible to those of actual accident situations.

  19. Vibration of safety injection pump motors

    International Nuclear Information System (INIS)

    Wattrelos, D.

    1996-01-01

    This paper covers a fault encountered in the safety injection pump motors of the French 900 MWe unit nuclear power stations. This fault was not revealed either during the low pressure safety injection and containment spray system pump qualification tests under accident conditions or during the special tests on a test bench carried out to attempt to replicate the fault and to identify ways of remedying it. This constitutes a potential common mode of failure of the safety injection system and the containment spray system pumps. The vibration phenomena illustrate the importance of carrying out tests in the plants under conditions as close as possible to those of actual accident situations

  20. Vibration of safety injection pump motors

    International Nuclear Information System (INIS)

    Wattrelos, D.

    1997-01-01

    This paper covers a fault encountered in the safety injection pump motors of the French 900 MWe unit nuclear power stations. This fault was not revealed either during the low pressure safety injection and containment spray system pump qualification test under accident conditions or during the special tests on a test bench carried out to attempt to replicate the fault and to identify ways of remedying it. This constitutes a potential common mode of failure of the safety injection system and the containment spray system pumps. The vibration phenomena illustrate the importance of carrying out test in the plants under conditions as close as possible to those of actual accident. (author)

  1. 7 CFR 1437.101 - Actual production history.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 10 2010-01-01 2010-01-01 false Actual production history. 1437.101 Section 1437.101... Determining Yield Coverage Using Actual Production History § 1437.101 Actual production history. Actual production history (APH) is the unit's record of crop yield by crop year for the APH base period. The APH...

  2. Natural Language Interface for Safety Certification of Safety-Critical Software

    Science.gov (United States)

    Denney, Ewen; Fischer, Bernd

    2011-01-01

    Model-based design and automated code generation are being used increasingly at NASA. The trend is to move beyond simulation and prototyping to actual flight code, particularly in the guidance, navigation, and control domain. However, there are substantial obstacles to more widespread adoption of code generators in such safety-critical domains. Since code generators are typically not qualified, there is no guarantee that their output is correct, and consequently the generated code still needs to be fully tested and certified. The AutoCert generator plug-in supports the certification of automatically generated code by formally verifying that the generated code is free of different safety violations, by constructing an independently verifiable certificate, and by explaining its analysis in a textual form suitable for code reviews.

  3. A Regulatory Perspective on the Performance and Reliability of Nuclear Passive Safety Systems

    International Nuclear Information System (INIS)

    Quan, Pham Trung; Lee, Sukho

    2016-01-01

    Passive safety systems have been proven to enhance the safety of NPPs. When an accident such as station blackout occurs, these systems can perform the following functions: the decay heat removal, passive safety injection, containment cooling, and the retention of radioactive materials. Following the IAEA definitions, using passive safety systems reduces reliance on active components to achieve proper actuation and not requiring operator intervention in accident conditions. That leads to the deviations in boundary conditions of the critical process or geometric parameters, which activate and operate the system to perform accident prevention and mitigation functions. The main difficulties in evaluation of functional failure of passive systems arise because of (a) lack of plant operational experience; (b) scarcity of adequate experimental data from integral test facilities or from separate effect tests in order to understand the performance characteristics of these passive systems, not only at normal operation but also during accidents and transients; (c) lack of accepted definitions of failure modes for these systems; and (d) difficulty in modeling certain physical behavior of these systems. Reliability assessment of the PSS is still one of the important issues. Several reliability methodologies such as REPAS, RMPS and ASPRA have been applied to the reliability assessments. However, some issues are remained unresolved due to lack of understanding of the treatment of dynamic failure characteristics of components of the PSS, the treatment of dynamic variation of independence process parameters such as ambient temperature and the functional failure criteria of the PSS. Dynamic reliability methodologies should be integrated in the PSS reliability analysis to have a true estimate of system failure probability. The methodology should estimate the physical variation of the parameters and the frequency of the accident sequences when the dynamic effects are considered

  4. The long-term safety and performance analyses of the surface disposal facility for the Belgian category a waste at Dessel

    Energy Technology Data Exchange (ETDEWEB)

    Cool, Wim; Vermarien, Elise; Wacquier, William [ONDRAF/NIRAS Avenue des Arts 14, BE-1210 Bruxelles (Belgium); Perko, Janez [SCK-CEN Boeretang 200, BE-2400 Mol (Belgium)

    2013-07-01

    ONDRAF/NIRAS, the Belgian Agency for Radioactive Waste and Enriched Fissile Materials, and its partners have developed long-term safety and performance analyses in the framework of the license application for a surface disposal facility for low level radioactive waste (category A waste) at Dessel, Belgium. This paper focusses on the methodology of the safety assessments and on key results from the application of this methodology. An overview is given (1) of the performance analyses for the containment safety function of the disposal system and (2) of the radiological impact analyses confirming that radiological impacts are below applicable reference values and constraints and leading to radiological criteria for the waste and the facility. In this discussion, multiple indicators for performance and safety are used to illustrate the multi-faceted nature of long-term performance and safety of the surface disposal. This contributes to the multiple lines of reasoning for confidence building that a positive decision to proceed to the next stage of construction is justified. (authors)

  5. Safety Performance Evaluations for the Vehicle Based Movable Barriers Using Full Scale Crash Tests

    Directory of Open Access Journals (Sweden)

    Jin Minsoo

    2017-01-01

    Full Text Available The present study aims to develop a prototype of large-size movable barriers to protect roadside workers from incoming vehicles to the road work area with the following functions: maximization of work space in the right and left directions, convenient mobility, and minimization of impact without modification of the inside of movable barriers into traffic lanes and perform safety performance assessment on passengers through full scale crash tests. The large movable barrier was divided into folder type and telescope type and the development stage was now at the prototype phase. A full scale crash test was conducted prior to certification test at a level of 90%. The full scale crash test result showed that both types of folder type movable barrier and telescope type movable barrier satisfied the standard of the passenger safety performance evaluation at a level of 90%.

  6. Road safety performance indicators : country profiles. SafetyNet, Building the European Road Safety Observatory, Workpackage 3, Deliverable 3.7b.

    NARCIS (Netherlands)

    Riguelle, F. Eksler, V. Holló, P. Morsink, P. Gent, A. van Gitelman, V. Assum, T. & Rackliff, L.

    2009-01-01

    The EC 6th Framework Integrated Project SafetyNet aims to accelerate the availability and use of harmonised road safety data in Europe. Having such data available throughout Europe would be tremendously beneficial for road safety, since it would enable the evaluation of road safety measures, the

  7. New reactor concepts. An analysis of the actual research status; Neue Reaktorkonzepte. Eine Analyse des aktuellen Forschungsstands

    Energy Technology Data Exchange (ETDEWEB)

    Pistner, Christoph; Englert, Matthias

    2017-04-15

    The report on new reactor concepts covers the following issues: characterization and survey of new reactor concepts; evaluation criteria: safety, resources for fuel supply, waste problems, economy and proliferation; comprehensive relevant aspects: thorium as alternative resource, partitioning and transmutation; actual developments and preliminary experiences for fast breeding reactor (FBR), high-temperature reactor (HTR), molten salt reactor (MSR), small modular reactor (SMR).

  8. Evaluation of Four Bedside Test Systems for Card Performance, Handling and Safety.

    Science.gov (United States)

    Giebel, Felix; Picker, Susanne M; Gathof, Birgit S

    2008-01-01

    SUMMARY: OBJECTIVE: Pretransfusion ABO compatibility testing is a simple and required precaution against ABO-incompatible transfusion, which is one of the greatest threats in transfusion medicine. While distinct agglutination is most important for correct test interpretation, protection against infectious diseases and ease of handling are crucial for accurate test performance. Therefore, the aim of this study was to evaluate differences in test card design, handling, and user safety. DESIGN: Four different bedside test cards with pre-applied antibodies were evaluated by 100 medical students using packed red blood cells of different ABO blood groups. Criteria of evaluation were: agglutination, labelling, handling, and safety regarding possible user injuries. Criteria were rated subjectively according to German school notes ranging from 1 = very good to 6 = very bad/insufficient. RESULTS: Overall, all cards received very good/good marks. The ABO blood group was identified correctly in all cases. Three cards (no. 1, no. 3, no. 4) received statistically significant (p labelling (1.5 vs. 2.2-2.4), handling (1.9-2.0 vs. 2.5), and user safety (2.5 vs. 3.4). Analysis of card self-explanation revealed no remarkable differences. CONCLUSION: Despite good performance of all card systems tested, the best results when including all criteria evaluated were obtained with card no. 4 (particularly concerning clear agglutination), followed by cards no. 2, no. 1, and no. 3.

  9. Comparison of in-plant performance test data with analytic prediction of reactor safety system injection transient (U)

    International Nuclear Information System (INIS)

    Roy, B.N.; Neill, C.H. Jr.

    1993-01-01

    This paper compares the performance test data from injection transients for both of the subsystems of the Supplementary Safety System of the Savannah River Site production reactor with analytical predictions from an in-house thermal hydraulic computer code. The code was initially developed for design validation of the new Supplementary Safety System subsystem, but is shown to be equally capable of predicting the performance of the Supplementary Safety System existing subsystem even though the two subsystem transient injections have marked differences. The code itself was discussed and its validation using prototypic tests with simulated fluids was reported in an earlier paper (Roy and Nomm 1991)

  10. Surprising Incentive: An Instrument for Promoting Safety Performance of Construction Employees

    Directory of Open Access Journals (Sweden)

    Fakhradin Ghasemi

    2015-09-01

    Conclusion: The results of this study proved that the surprising incentive would improve the employees' safety performance just in the short term because the surprising value of the incentives dwindle over time. For this reason and to maintain the surprising value of the incentive system, the amount and types of incentives need to be evaluated and modified annually or biannually.

  11. Safety of light water reactors. Risks of nuclear technology

    International Nuclear Information System (INIS)

    Veser, Anke; Schlueter, Franz-Hermann; Raskob, Wolfgang; Landman, Claudia; Paesler-Sauer, Juergen; Kessler, Guenter

    2012-01-01

    The book on the safety of light-water reactors includes the following chapters: Part I: Physical and technical safety concept of actual German and future European light-water reactors: (1) Worldwide operated nuclear power plants in 2011, (2) Some reactor physical fundamentals. (3) Nuclear power plants in Germany. (4) Radioactive exposure due to nuclear power plants. (5) Safety concept of light-water reactors. (6) Probabilistic analyses and risk studies. (7) Design of light-water reactors against external incidents. (8) Risk comparison of nuclear power plants and other energy systems. (9) Evaluation of risk studies using the improved (new) safety concept for LWR. (19) The severe reactor accidents of Three Mile Island, Chernobyl and Fukushima. Part II: Safety of German LWR in case of a postulated aircraft impact. (11) Literature. (12) Review of requirements and actual design. (13) Incident scenarios. (14) Load approach for aircraft impact. (15) Demonstration of the structural behavior in case of aircraft impact. (16) Special considerations. (17) Evaluation of the safety state of German and foreign nuclear power plants. Part III: ROSOS as example for a computer-based decision making support system for the severe accident management. (19) Literature. (20) Radiological fundamentals, accident management, modeling of the radiological situation. (21) The decision making support system RODOS. (22) RODOS and the Fukushima accident. (23) Recent developments in the radiological emergency management in the European frame.

  12. Caffeine-based food supplements and beverages: Trends of consumption for performance purposes and safety concerns.

    Science.gov (United States)

    Bessada, Sílvia M F; Alves, Rita C; Oliveira, M Beatriz P P

    2018-07-01

    Nowadays, daily food supplementation regarding the improvement of physical and mental performance is a growing trend in sport practitioners, young students and active people. Food supplements are foodstuffs, labeled under food law and not obliged to safety assessments before their commercialization. Several products are commercialized claiming ergogenic effects as marketing strategies. Caffeine is often one of their main ingredients, as it increases both physical performance and concentration. This manuscript presents a general overview of the current caffeine-based food supplements and energy drinks available in the Portuguese market, as well as the consuming trends regarding their ergogenic effects, performance purposes, and active ingredients. Product claims, recommended daily intakes, caffeine pharmacology, and safety concerns aspects are also discussed aspects. Copyright © 2018 Elsevier Ltd. All rights reserved.

  13. Contractor safety

    International Nuclear Information System (INIS)

    Blanton, M.L.; Montgomery, E.W.

    1991-01-01

    The recent trend in the United States and Shell Oil Company EandP has been to increase use of contractors to do specialized work. Many companies now use contractors almost exclusively for operations such as drilling, well workovers, construction, and many specialty and routine maintenance tasks. Today, approximately 75% of Shell Oil Company's actual operating work force in EandP is contract. Clearly, HSandE considerations must become an increasingly important part of the contractor selection process. This paper reports on the Shell Oil Company's evolution from a bidder selection process to a program of Matching Owner and Contractor. Well has begun to expand efforts to make better assessments of contractor's HSandE capabilities and values in pre-bid considerations. Focus is on pre-bid evaluations to select contractors that have strong HSandE commitments and values. Contractor safety performance in this industry must be brought up to the same standards as operating companies. In Shell Oil EandP is only willing to contractors who can and are willing to do that

  14. Safety culture in nuclear installations. Guidance for the use in enhancement of safety culture

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-12-01

    IAEA Assessment of the Safety Culture in Organizations Team (ASCOT) activities, significant work has been done with respect to indicators to determine the effectiveness of safety culture. IAEA-TECDOC-860, ASCOT Guidelines, issued in 1996, proposed key indicators for the different areas that need to be considered when assessing safety culture. A number of other INSAG reports and Safety Series reports have been published by the IAEA to provide information that will be helpful to organizations that are interested in developing or enhancing their safety culture. Recently the IAEA perspective on safety culture has broadened even further with attention focused on obtaining a deeper understanding of the actual concept of culture and particularly organizational culture. The approach supplements the IAEA previous efforts to promote a better understanding of safety culture, but does not replace them. It can be argued that the IAEA perspective of safety culture has evolved in stages. The first stage was associated with the definition of safety culture; the second stage with how to assess it; the third stage on how to enhance it; and the fourth and current stage on obtaining a deeper understanding of the actual concept of culture. The hope is that the more sophisticated understanding obtained in the fourth stage will lead to improved ways of assessing safety culture, and also increase our ability to detect changes in safety culture at an early point in time. This ability will enable corrective actions to be taken to avoid the consequences of a deteriorating safety culture.

  15. Safety culture in nuclear installations. Guidance for the use in enhancement of safety culture

    International Nuclear Information System (INIS)

    2002-12-01

    IAEA Assessment of the Safety Culture in Organizations Team (ASCOT) activities, significant work has been done with respect to indicators to determine the effectiveness of safety culture. IAEA-TECDOC-860, ASCOT Guidelines, issued in 1996, proposed key indicators for the different areas that need to be considered when assessing safety culture. A number of other INSAG reports and Safety Series reports have been published by the IAEA to provide information that will be helpful to organizations that are interested in developing or enhancing their safety culture. Recently the IAEA perspective on safety culture has broadened even further with attention focused on obtaining a deeper understanding of the actual concept of culture and particularly organizational culture. The approach supplements the IAEA previous efforts to promote a better understanding of safety culture, but does not replace them. It can be argued that the IAEA perspective of safety culture has evolved in stages. The first stage was associated with the definition of safety culture; the second stage with how to assess it; the third stage on how to enhance it; and the fourth and current stage on obtaining a deeper understanding of the actual concept of culture. The hope is that the more sophisticated understanding obtained in the fourth stage will lead to improved ways of assessing safety culture, and also increase our ability to detect changes in safety culture at an early point in time. This ability will enable corrective actions to be taken to avoid the consequences of a deteriorating safety culture

  16. Nuclear Safety Authority independence, progresses to be considered

    International Nuclear Information System (INIS)

    Delzangles, Hubert

    2013-01-01

    The Nuclear Safety Authority is an independent administrative body. Nevertheless, functional and organic independence from operators and government can have different degrees. Having a look on the actual context, where government holds a large part of the main nuclear French operators, independence has to be maximal in order to avoid any conflict of interest that could attempt to nuclear safety. In a global point of view, it is possible to think about the risks or the benefits of the institutionalized cooperation between national regulators on the necessary independence of the Nuclear Safety Authority

  17. Importance of human factors on nuclear installations safety

    International Nuclear Information System (INIS)

    Caruso, G.J.

    1990-01-01

    Actually, installations safety and, in particular the nuclear installations infer a strong incidence in human factors related to the design and operation of such installations. In general, the experience aims to that the most important accidents have happened as result of the components' failures combination and human failures in the operation of safety systems. Human factors in the nuclear installations may be divided into two areas: economy and human reliability. Human factors treatments for the safety evaluation of the nuclear installations allow to diagnose the weak points of man-machine interaction. (Author) [es

  18. Development and application of digital safety system in NPPs

    International Nuclear Information System (INIS)

    Kwon, Keechoon; Kim, Changhwoi; Lee, Dongyoung

    2012-01-01

    This paper describes the development of digital safety system in NPPs based on safety- grade programmable logic controller (PLC) platform and its application to real NPP construction. The digital safety system consists of a reactor protection system and an engineered safety feature-component control system. The safety-grade PLC platform was developed so that it meets the requirements of the regulation. The PLC consists of various modules such as a power module, a processor module, communication modules, digital input/output modules, analog input/output modules, a LOCA bus extension module, and a high-speed pulse counter module. The reactor protection system is designed with a redundant 4-channel architecture, and every channel is implemented with the same architecture. A single channel consists of a redundant bi-stable processor, a redundant coincidence processor, an automatic test and interface processor, and a cabinet operator module. The engineered safety feature-component control system is designed with four redundant divisions, and implemented with the PLC platform. The principal components of an individual division are fault tolerant group controllers, loop controllers, a test and interface processor, a cabinet operator module and a control channel gateway. The topical report is submitted to the regulatory body, and got safety evaluation report from the regulatory body. Also, the developed system is tested in the integrated performance validation facility. It is decided that the digital safety system applied to Shin-Uljin unit 1 and 2 after a topical report approval and validation test. Design changes occur in the digital safety system that is applied to an actual nuclear power plant construction, and the PLC has also been upgraded

  19. Development and application of digital safety system in NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Keechoon; Kim, Changhwoi; Lee, Dongyoung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-03-15

    This paper describes the development of digital safety system in NPPs based on safety- grade programmable logic controller (PLC) platform and its application to real NPP construction. The digital safety system consists of a reactor protection system and an engineered safety feature-component control system. The safety-grade PLC platform was developed so that it meets the requirements of the regulation. The PLC consists of various modules such as a power module, a processor module, communication modules, digital input/output modules, analog input/output modules, a LOCA bus extension module, and a high-speed pulse counter module. The reactor protection system is designed with a redundant 4-channel architecture, and every channel is implemented with the same architecture. A single channel consists of a redundant bi-stable processor, a redundant coincidence processor, an automatic test and interface processor, and a cabinet operator module. The engineered safety feature-component control system is designed with four redundant divisions, and implemented with the PLC platform. The principal components of an individual division are fault tolerant group controllers, loop controllers, a test and interface processor, a cabinet operator module and a control channel gateway. The topical report is submitted to the regulatory body, and got safety evaluation report from the regulatory body. Also, the developed system is tested in the integrated performance validation facility. It is decided that the digital safety system applied to Shin-Uljin unit 1 and 2 after a topical report approval and validation test. Design changes occur in the digital safety system that is applied to an actual nuclear power plant construction, and the PLC has also been upgraded.

  20. Development of 4S and related technologies. (3) Statistical evaluation of safety performance of 4S on ULOF event

    International Nuclear Information System (INIS)

    Ishii, Kyoko; Matsumiya, Hisato; Horie, Hideki; Miyagi, Kazumi

    2009-01-01

    The purpose of this work is to evaluate quantitatively and statistically the safety performance of Super-Safe, Small, and Simple reactor (4S) by analyzing with ARGO code, a plant dynamics code for a sodium-cooled fast reactor. In this evaluation, an Anticipated Transient Without Scram (ATWS) is assumed, and an Unprotected Loss of Flow (ULOF) event is selected as a typical ATWS case. After a metric concerned with safety design is defined as performance factor a Phenomena Identification Ranking Table (PIRT) is produced in order to select the plausible phenomena that affect the metric. Then a sensitivity analysis is performed for the parameters related to the selected plausible phenomena. Finally the metric is evaluated with statistical methods whether it satisfies the given safety acceptance criteria. The result is as follows: The Cumulative Damage Fraction (CDF) for the cladding is defined as a metric, and the statistical estimation of the one-sided upper tolerance limit of 95 percent probability at a 95 percent confidence level in CDF is within the safety acceptance criterion; CDF < 0.1. The result shows that the 4S safety performance is acceptable in the ULOF event. (author)

  1. Actual situation of radioactive waste management in Guatemala

    International Nuclear Information System (INIS)

    Gomez O, P.

    1996-01-01

    This paper focuses on the actual radioactive waste management situation in Guatemala, as well as on the sources and facilities that have obtained the license, and the way to disposal them, when they are considered as radioactive waste. The Direccion General de Energia Nuclear is the entity responsible for the proper and normal performance of the regulatory activity in the country. (author). 3 refs

  2. Performance Measurement and Target-Setting in California's Safety Net Health Systems.

    Science.gov (United States)

    Hemmat, Shirin; Schillinger, Dean; Lyles, Courtney; Ackerman, Sara; Gourley, Gato; Vittinghoff, Eric; Handley, Margaret; Sarkar, Urmimala

    Health policies encourage implementing quality measurement with performance targets. The 2010-2015 California Medicaid waiver mandated quality measurement and reporting. In 2013, California safety net hospitals participating in the waiver set a voluntary performance target (the 90th percentile for Medicare preferred provider organization plans) for mammography screening and cholesterol control in diabetes. They did not reach the target, and the difference-in-differences analysis suggested that there was no difference for mammography ( P = .39) and low-density lipoprotein control ( P = .11) performance compared to measures for which no statewide quality improvement initiative existed. California's Medicaid waiver was associated with improved performance on a number of metrics, but this performance was not attributable to target setting on specific health conditions. Performance may have improved because of secular trends or systems improvements related to waiver funding. Relying on condition-specific targets to measure performance may underestimate improvements and disadvantage certain health systems. Achieving ambitious targets likely requires sustained fiscal, management, and workforce investments.

  3. Associations between skill perceptions and young children's actual fundamental movement skills.

    Science.gov (United States)

    Liong, Grace H E; Ridgers, Nicola D; Barnett, Lisa M

    2015-04-01

    Given that children with low movement skill competence engage in less physical activity, it is important to understand how children's perceptions relate to actual movement competence. This study examined relationships between (i) children's self-perception and objective assessments of their movement skills (object control and locomotor) and (ii) parents' perceptions of the children's movement skills and objective assessment. Children's skill perceptions were assessed using the Pictorial Scale of Perceived Movement Skill Competence for Young Children. Parent perceptions of their child's skills were assessed using a modified version of this instrument. The Test of Gross Motor Development-2nd edition assessed children's skills objectively. Participants were 136 Australian children (51% boys; M=6.5 yr., SD=1.1) and 133 parents. Regression analyses (by sex) examined the relationship between perceptions and children's scores for actual skilled performance. Boys' perceptions were associated with their actual object control ability. Parents accurately perceived boys' object control ability and girls' locomotor ability, but not the reverse. This suggests interventions aiming to improve children's movement skills could target parents and be designed to teach parents how to recognize good and poor skill performance in their children.

  4. Study of In-Pile test facility for fast reactor safety research: performance requirements and design features

    Energy Technology Data Exchange (ETDEWEB)

    Nonaka, N.; Kawatta, N.; Niwa, H.; Kondo, S.; Maeda, K

    1996-12-31

    This paper describes a program and the main design features of a new in-pile safety facility SERAPH planned for future fast reactor safety research. The current status of R and D on technical developments in relation to the research objectives and performance requirements to the facility design is given.

  5. Theoretical vs. actual energy consumption of labelled dwellings in the Netherlands: Discrepancies and policy implications

    International Nuclear Information System (INIS)

    Majcen, D.; Itard, L.C.M.; Visscher, H.

    2013-01-01

    In Europe, the Energy Performance of Buildings Directive (EPBD) provides for compulsory energy performance certification (labelling) for all existing dwellings. In the Netherlands, a labelling scheme was introduced in 2008. Certificates contain the energy label of the dwelling and corresponding theoretical gas and electricity consumption, calculated based on the dwellings physical characteristics, its heating, ventilation and cooling systems and standard use characteristics. This paper reports on a large-scale study of around 200,000 dwellings comparing labels and theoretical energy use with data on actual energy use. The study shows that dwellings with a low energy label actually consume much less energy than predicted by the label, but on the other hand, energy-efficient dwellings consume more than predicted. In practice, policy targets are set according to the theoretical rather than the actual consumptions of the building stock. In line with identified discrepancies, the study shows that whereas most energy reduction targets can be met according to the theoretical energy consumption of the dwelling stock, the future actual energy reduction potential is much lower and fails to meet most of the current energy reduction targets. - Highlights: ► Actual gas consumption in Dutch dwellings is lower than the theoretical. ► In the dwellings with label A–B, theoretical gas consumption is lower than actual gas consumption. ► In less efficient dwellings, theoretical gas consumption is much higher than the actual. ► Most current energy reduction targets are unachievable if modelled with actual instead of theoretical energy consumption

  6. An investigation into the actual condition of radiation safety control

    International Nuclear Information System (INIS)

    Katsurayama, Kosuke

    1976-01-01

    The result of investigation on the real condition of radiation safety control is reported with some considerations. The investigation was made in April, 1975, by means of questionnaires to 418 companies, and the responses were obtained from 126 companies, i.e. 11 research laboratories, 98 manufacturing factories, and 17 inspection facilities. The average integrated dose in the inspection facilities was 0.91 rem/year, the most among three. The exposure dose in most of the research laboratories and manufacturing factories investigated was within the limit of 0.5 rem/year, and that in the inspection facilities was distributed over from the background level to 5 rem/year. The ratios of the workers engaged in radiation operation and the workers possessing the licences related to non-destructive examination to all employees were investigated, but they were not at satisfactory level. Regarding the abandonment of radioactive isotopes, 63.5% of the companies answered deliver the radioactive isotopes to be abandoned to Japan Isotope Association, and 25.7% let equipment makers to take them back. As for the education and training of operators for the safe treatment of radioactive substances and the prevention of accidents, most of the companies answered gave the education once or twice a year, and to those who just entered the companies, but more substantial education in desirable. (Nishino, S.)

  7. Safety Performance Indicator for alcohol in road accidents--international comparison, validity and data quality.

    Science.gov (United States)

    Assum, Terje; Sørensen, Michael

    2010-03-01

    Safety Performance Indicators, SPIs, are developed for various areas within road safety such as speed, car occupant protection, alcohol and drugs, vehicle safety, etc. SPIs can be used to indicate the road safety situation and to compare road safety performance between countries and over time and to understand the process leading to accidents, helping to select the measures to reduce them. This article describes an alcohol SPI defined as the percentage of fatalities resulting from accidents involving at least one driver impaired by alcohol. The calculation of the alcohol SPI for 26 European countries shows that the SPI varies from 4.4% in Bulgaria to 72.2% in Italy. These results raise the question if the results reflect the real situation or if there is a methodological explanation. To answer this question three different studies were carried out: comparison with other alcohol SPIs, in-depth studies of data quality in seven selected countries, and a study of correlations between the SPI and influencing factors. These studies indicate clearly that there is a need to improve quality of the data used for the alcohol SPI. Most importantly, the total number of drivers involved in fatal accidents, the number tested for alcohol and the number not tested, should be reported, in addition to the number of alcohol positive and negative drivers among those tested. Until these improvements are made, the validity of this SPI seems poor and comparison of the alcohol SPI results across countries should be made with caution. Copyright 2009 Elsevier Ltd. All rights reserved.

  8. Safety performance evaluation of cable median barriers on freeways in Florida.

    Science.gov (United States)

    Alluri, Priyanka; Haleem, Kirolos; Gan, Albert; Mauthner, John

    2016-07-03

    This article aims to evaluate the safety performance of cable median barriers on freeways in Florida. The safety performance evaluation was based on the percentages of barrier and median crossovers by vehicle type, crash severity, and cable median barrier type (Trinity Cable Safety System [CASS] and Gibraltar system). Twenty-three locations with cable median barriers totaling about 101 miles were identified. Police reports of 6,524 crashes from years 2005-2010 at these locations were reviewed to verify and obtain detailed crash information. A total of 549 crashes were determined to be barrier related (i.e., crashes involving vehicles hitting the cable median barrier) and were reviewed in further detail to identify crossover crashes and the manner in which the vehicles crossed the barriers; that is, by either overriding, underriding, or penetrating the barriers. Overall, 2.6% of vehicles that hit the cable median barrier crossed the median and traversed into the opposite travel lane. Overall, 98.1% of cars and 95.5% of light trucks that hit the barrier were prevented from crossing the median. In other words, 1.9% of cars and 4.5% of light trucks that hit the barrier had crossed the median and encroached on the opposite travel lanes. There is no significant difference in the performance of cable median barrier for cars versus light trucks in terms of crossover crashes. In terms of severity, overrides were more severe compared to underrides and penetrations. The statistics showed that the CASS and Gibraltar systems performed similarly in terms of crossover crashes. However, the Gibraltar system experienced a higher proportion of penetrations compared to the CASS system. The CASS system resulted in a slightly higher percentage of moderate and minor injury crashes compared to the Gibraltar system. Cable median barriers are successful in preventing median crossover crashes; 97.4% of the cable median barrier crashes were prevented from crossing over the median. Of all of

  9. A look at new key performance criteria that could most affect the safety of long term storage of nuclear waste. A case study commissioned by CEA

    International Nuclear Information System (INIS)

    Marvy, A.; Lioure, A.; Heriard-Dubreuil, G.; Gadbois, S.; Schneider, T.; Schieber, C

    2002-01-01

    As part of the work scope set in the French law on high level long lived waste R and D passed in 1991, CEA is conducting research work to establish the scientific basis and assess the feasibility of long term storage as an option for the safe management of nuclear waste for periods as long as a few centuries. This goal is a significant departure from current industrial practice where storage facilities are usually built to last only a few decades. From a technical viewpoint such an extension in time seems feasible provided care and maintenance is exercised. Considering such long periods of time risk for Society of loosing oversight and control of such a facility is real which triggers the question of whether and how long term storage safety can be actually achieved. Therefore CEA commissioned a study in which MUTADIS Consultants and CEPN were both involved. The case study looks into several past and actual human enterprises conducted over significant periods of time - one dating back to the end of the 18th century - and identified off the nuclear field. Then-prevailing societal behaviour and organizational structures are screened out to show how they were and are still able to cope with similar oversight and control goals. As a result the study group obtained a set of performance criteria relating to issues like responsibility, securing funds, legal and legislative implications, economic sustainable development, all being areas which are not traditionally considered when technical studies are conducted. These criteria can be most useful from the design stage onward, first in an attempt to define the facility construction and operating guiding principles, and thereafter to substantiate the safety case for long term storage and get geared to the public dialogue on that undertaking should it become a reality. (author)

  10. Health and Safety Guide for Home Performance Contractors

    Energy Technology Data Exchange (ETDEWEB)

    Stratton, Chris [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Walker, Iain S. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2012-02-15

    This report is intended to provide home performance contractor trainers with a resource to keep both their workers and home residents safe and healthy. This document is an attempt to describe what we currently believe is safe, what we believe is unsafe, and what we’re unsure about. It is intended to identify health and safety issues and provide historical context and current understanding of both risks and mitigation strategies. In addition, it provides links to more in-depth resources for each issue. When we tighten the thermal envelope of a house to improve comfort and reduce energy use, we have to be sure that we are not compromising the indoor air quality of the home. This means identifying and mitigating or eliminating pollution sources before and after you make changes to the home. These sources can include materials and finishes in the home, exhaust gasses from combustion appliances, soil gasses such as radon, and moisture from a bathroom, kitchen, or unvented clothes dryer. Our first responsibility is to do no harm — this applies both to our clients and to our employees. Currently, there are many new products that are widely used but whose health effects are not well understood. Our in ability to have perfect information means the directive to do no harm can be difficult to obey. Each home is a little bit different, and in the face of a situation you’ve never encountered, it’s important to have a solid grasp of the fundamental concepts of building science when the hard and fast rules don’t apply . The home performance industry is gaining momentum, and has the potential to expand greatly as energy costs continue to rise. It is imperative that we remain vigilant about protecting the health and safety of our workers and our customers. It only takes a few news stories about a family that got sick after their home was tightened by a home performance contractor to scare off potential customers and taint the reputation of the entire industry. Good

  11. Tools for the performance assessment and improvement of food safety management systems ; review

    NARCIS (Netherlands)

    Jacxsens, L.; Luning, P.A.; Marcelis, W.J.; Boekel, van M.A.J.S.; Rovira, J.; Oses Gomez, S.; Kousta, M.; Drosinos, E.H.; Jasson, V.; Uyttendaele, M.

    2011-01-01

    Food business operators are challenged to combine requirements from different stakeholders (e.g. government, retailers) into a company specific Food Safety Management System (FSMS). Tools to diagnose the performance of an implemented FSMS (diagnostic tools), tools to help a selection process

  12. Advanced liquid waste processing technologies: Theoretical versus actual application

    International Nuclear Information System (INIS)

    Barker, Tracy A.

    1992-01-01

    This paper provides an overview of Chem-Nuclear Systems, Inc. (CNSI) experience with turn-key chromate removal at the Maine Yankee Nuclear Plant. Theoretical and actual experiences are addressed on topics such as processing duration, laboratory testing, equipment requirements, chromate removal, waste generation, and waste processing. Chromate salts are used in industrial recirculation cooling water systems as a corrosion inhibitor. However, chromates are toxic at concentrations necessary for surface inhibition. As a result, Chem-Nuclear was contracted to perform turn-key chromate removal and waste disposal by demineralization. This project was unique in that prior to on-site mobilization, a composite sample of chromated waste was shipped to CNSI laboratories for treatment through a laboratory scale system. Removal efficiency, process media requirements, and waste processing methodology were determined from this laboratory testing. Samples of the waste resulting from this testing were processed by dewatering and solidification, respectively. TCLP tests were performed on the actual processed waste, and based on the TCLP results, pre-approval for media waste disposal was obtained. (author)

  13. The actual citation impact of European oncological research.

    Science.gov (United States)

    López-Illescas, Carmen; de Moya-Anegón, Félix; Moed, Henk F

    2008-01-01

    This study provides an overview of the research performance of major European countries in the field Oncology, the most important journals in which they published their research articles, and the most important academic institutions publishing them. The analysis was based on Thomson Scientific's Web of Science (WoS) and calculated bibliometric indicators of publication activity and actual citation impact. Studying the time period 2000-2006, it gives an update of earlier studies, but at the same time it expands their methodologies, using a broader definition of the field, calculating indicators of actual citation impact, and analysing new and policy relevant aspects. Findings suggest that the emergence of Asian countries in the field Oncology has displaced European articles more strongly than articles from the USA; that oncologists who have published their articles in important, more general journals or in journals covering other specialties, rather than in their own specialist journals, have generated a relatively high actual citation impact; and that universities from Germany, and--to a lesser extent--those from Italy, the Netherlands, UK, and Sweden, dominate a ranking of European universities based on number of articles in oncology. The outcomes illustrate that different bibliometric methodologies may lead to different outcomes, and that outcomes should be interpreted with care.

  14. Safety evaluation report on Tennessee Valley Authority: Browns Ferry nuclear performance plan

    International Nuclear Information System (INIS)

    1989-10-01

    This safety evaluation report (SER) on the information submitted by the Tennessee Valley Authority (TVA) in its Nuclear Performance Plan, through Revision 2, for the Browns Ferry Nuclear Plant and in supporting documents has been prepared by the US Nuclear Regulatory commission staff. The Browns Ferry Nuclear Plant consists of three boiling-water reactors at a site in Limestone County, Alabama. The plan addresses the plant-specific concerns requiring resolution before the startup of Unit 2. The staff will inspect implementation of those TVA programs that address these concerns. Where systems are common to Units 1 and 2 or to Units 2 and 3, the staff safety evaluations of those systems are included herein. 85 refs

  15. Safety evaluation report on Tennessee Valley Authority: Watts Bar Nuclear Performance Plan

    International Nuclear Information System (INIS)

    1990-01-01

    This safety evaluation report on the information submitted by the Tennessee Valley Authority in its Nuclear Performance Plan for the Watts Bar Nuclear Plant and in supporting documents has been prepared by the US Nuclear Regulatory Commission staff. The plan addresses the plant-specific corrective actions as part of the recovery program for licensing of Unit 1. The staff will be monitoring and inspecting the implementation of the programs. The plan does not address all licensing matters that will be required for fuel load and operation of Unit 1. Those remaining licensing matters have been addressed in previous safety evaluations or will be addressed in accordance with routing NRC licensing practices. 97 refs

  16. Associations between young children's perceived and actual ball skill competence and physical activity.

    Science.gov (United States)

    Barnett, Lisa M; Ridgers, Nicola D; Salmon, Jo

    2015-03-01

    The relationship between actual and perceived object control competence (ball skills) and the contribution to young children's physical activity is not known. Cross sectional study. The Test Gross Motor Development-2 assessed actual object control competence and a modified version of the Pictorial Scale of Perceived Competence and Social Acceptance for Young Children assessed perceived object control competence. Moderate- to vigorous-intensity physical activity was measured via accelerometry. Three mixed regression models were performed: (i) object control competence as the predictor and the outcome as perceived object control, (ii) perceived object control competence as the predictor and the outcome moderate to vigorous physical activity and (iii) actual object control as the predictor and the outcome moderate to vigorous physical activity. Models adjusted for school clustering, monitor wear time, sex and age. Interactions between respective predictor variables and sex were performed if warranted. A total of 102 children (56% boys, 44% girls) aged 4-8 years (M 6.3, SD 0.92) completed assessments. Girls had lower perceived and actual object control competence and were less active than boys. Actual object control competence was positively associated with perceived object control competence (B=0.11, t(96)=2.25, pperceived object control competence (p=0.827) were associated with moderate to vigorous physical activity. Young children's perceived ball skill abilities appear to relate to actual competence; however, these measures were not associated with physical activity. In older children, object control skill is associated with physical activity so targeting young children's object control skills is an intervention priority. Crown Copyright © 2014. Published by Elsevier Ltd. All rights reserved.

  17. Application of Advanced Technology to Improve Plant Performance. Safety and Performance in Current NPPs

    International Nuclear Information System (INIS)

    Hashemian, H.M.

    2011-01-01

    Advances in computer technologies, signal processing, analytical modeling, and the advent of wireless sensors have provided the nuclear industry with ample means to automate and optimize maintenance activities and improve safety, efficiency, and availability, while reducing costs and radiation exposure to maintenance personnel. This paper provides a review of these developments and presents examples of their use in the nuclear power industry and the financial and safety benefits that they have produced. As the current generation of nuclear power plants have passed their mid-life, increased monitoring of their health is critical to their safe operation. This is especially true now that license renewal of nuclear power plants has accelerated, allowing some plants to operate up to 60 years or more. Furthermore, many utilities are maximizing their power output through uprating projects and retrofits. This puts additional demand and more stress on the plant equipment such as the instrumentation and control (I and C) systems and the reactor internal components making them more vulnerable to the effects of aging, degradation, and failure. In the meantime, the nuclear power industry is working to reduce generation costs by adopting condition-based maintenance strategies and automation of testing activities. These developments have stimulated great interest in on-line monitoring (OLM) technologies and new diagnostic and prognostic methods to anticipate, identify, and resolve equipment and process problems and ensure plant safety, efficiency, and immunity to accidents. The foundation for much of the required technologies has already been established through 40 years of research and development (R and D) efforts performed by numerous organizations, scientists, and engineers around the world including the author. This paper provides examples of these technologies and demonstrates how the gap between some of the more important R and D efforts and end users have been filled

  18. Nuclear safety: operational aspects. 1. Demonstrating the Link Between Safety Culture and Competitiveness

    International Nuclear Information System (INIS)

    Chakoff, H. Elliot; Slider, James E.

    2001-01-01

    by the inspectors and provided a wholly objective basis for evaluating performance. The follow-up study examined the long-term survivability of the 12 plants to determine the efficacy of the methodology in the presence of confounding factors, such as changes in the regulatory and economic environment. The current status of each plant was identified and compared to the status of that plant during the pilot study. For plants that shut down, we evaluated the factors that led to closure according to the methodology employed in the pilot study. Nonparametric statistical methods were employed to determine the difference in risk of early closure. Four of the 12 pilot plants closed during the 20-yr interval. The closures reflect a variety of factors, but those within the control of management predominate. Thus, Table I shows that plants identified as poorer performers experienced a 20-yr risk of early closure approximately ten times higher than plants identified as better performers. Given there was only a 5% chance that a plant identified as a better performer was actually a poorer performer, time has validated the metrics and methodology. During the past 20 yr, the industry has changed remarkably. The poor-performance risk factor has thinned the ranks of plants and operators such that the bulk of surviving plants are good performers. The poor-performance risk factor once dominated by regulatory considerations is now dominated by the influences of a Darwinian marketplace. Lessons learned in the development and followup of this methodology indicate that well-designed performance evaluation tools can provide insight into the business risk presented by a plant and establish a quantitative basis for control of safety culture and performance. (authors)

  19. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management. Report of the Federal Republic of Germany for the sixth review meeting in May 2018

    International Nuclear Information System (INIS)

    2017-08-01

    The joint convention on the safety of spent fuel management and on the safety of radioactive waste management covers the following topics: historical development and actual status of the civil use of nuclear power, politics and the spent fuel management, inventories and listing, legislation and executive systems, other safeguard regulations, safety during spent fuel handling, safety during radioactive waste processing, transport across national borders, disused enclosed radioactive sources, general regulations for safety enhancement.

  20. Perspectives on reactor safety. Revision 1

    International Nuclear Information System (INIS)

    Haskin, F.E.; Hodge, S.A.

    1997-11-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

  1. Perspectives on reactor safety. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A. [Oak Ridge National Lab., TN (United States). Engineering Technology Div.

    1997-11-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

  2. Beyond safety accountability

    CERN Document Server

    Geller, E Scott

    2001-01-01

    Written in an easy-to-read conversational tone, Beyond Safety Accountability explains how to develop an organizational culture that encourages people to be accountable for their work practices and to embrace a higher sense of personal responsibility. The author begins by thoroughly explaining the difference between safety accountability and safety responsibility. He then examines the need of organizations to improve safety performance, discusses why such performance improvement can be achieved through a continuous safety process, as distinguished from a safety program, and provides the practic

  3. Evaluation of safety, performance and emissions of synthetic fuel blends in a Cessna Citation II

    NARCIS (Netherlands)

    Snijders, T.A.; Melkert, J.A.

    2011-01-01

    Prior to being used in aviation, alternative fuels have to be tested thoroughly to ensure safe operation. At Delft University of Technology, a test programme was performed to evaluate the safety, performance and emissions of synthetic fuel blends. During test preparations, compatibility of the

  4. Performances of 250 Amp-hr lithium/thionyl chloride cells

    Science.gov (United States)

    Goualard, Jacques

    1991-01-01

    A 250 Ah lithium thionyl chloride battery is being developed for a booster rocket engine. Extensive cell testing is running to evaluate functional and safety performances. Some results are presented. The lithium/thionyl chloride batteries were selected for their high energy density (low weight) as compared to other sources. The temperature of a lower weight item will be more sensitive to variations of internal and external heat fluxes than a heavier one. The use of high energy density L/TC batteries is subjected to stringent thermal environments to have benefit of energy density and to stay safe in any conditions. The battery thermal environment and discharge rate have to be adjusted to obtain the right temperature range at cell level, to have the maximum performances. Voltage and capacity are very sensitive to temperature. This temperature is the cell internal actual temperature during discharge. This temperature is directed by external thermal environment and by cell internal heat dissipation, i.e., cell actual voltage.

  5. Performances of 250 Amp-hr lithium/thionyl chloride cells

    Science.gov (United States)

    Goualard, Jacques

    1991-05-01

    A 250 Ah lithium thionyl chloride battery is being developed for a booster rocket engine. Extensive cell testing is running to evaluate functional and safety performances. Some results are presented. The lithium/thionyl chloride batteries were selected for their high energy density (low weight) as compared to other sources. The temperature of a lower weight item will be more sensitive to variations of internal and external heat fluxes than a heavier one. The use of high energy density L/TC batteries is subjected to stringent thermal environments to have benefit of energy density and to stay safe in any conditions. The battery thermal environment and discharge rate have to be adjusted to obtain the right temperature range at cell level, to have the maximum performances. Voltage and capacity are very sensitive to temperature. This temperature is the cell internal actual temperature during discharge. This temperature is directed by external thermal environment and by cell internal heat dissipation, i.e., cell actual voltage.

  6. Nuclear criticality safety: 3-day training course

    International Nuclear Information System (INIS)

    Schlesser, J.A.

    1993-06-01

    The open-quotes 3-Day Training Courseclose quotes is an intensive course in criticality safety consisting of lectures and laboratory sessions, including active student participation in actual critical experiments, a visit to a plutonium processing facility, and in-depth discussions on safety philosophy. The program is directed toward personnel who currently have criticality safety responsibilities in the capacity of supervisory staff and/or line management. This compilation of notes is presented as a source reference for the criticality safety course. It represents the contributions of many people, particularly Tom McLaughlin, the course's primary instructor. It should be noted that when chapters were extracted, an attempt was made to maintain footnotes and references as originally written. Photographs and illustrations are numbered sequentially

  7. Do Performance-Safety Tradeoffs Cause Hypometric Metabolic Scaling in Animals?

    Science.gov (United States)

    Harrison, Jon F

    2017-09-01

    Hypometric scaling of aerobic metabolism in animals has been widely attributed to constraints on oxygen (O 2 ) supply in larger animals, but recent findings demonstrate that O 2 supply balances with need regardless of size. Larger animals also do not exhibit evidence of compensation for O 2 supply limitation. Because declining metabolic rates (MRs) are tightly linked to fitness, this provides significant evidence against the hypothesis that constraints on supply drive hypometric scaling. As an alternative, ATP demand might decline in larger animals because of performance-safety tradeoffs. Larger animals, which typically reproduce later, exhibit risk-reducing strategies that lower MR. Conversely, smaller animals are more strongly selected for growth and costly neurolocomotory performance, elevating metabolism. Copyright © 2017 Elsevier Ltd. All rights reserved.

  8. Coffee Shop As a Media for Self-Actualization Today's Youth

    Directory of Open Access Journals (Sweden)

    Salendra Salendra

    2014-07-01

    Full Text Available Trends go to a coffee shop that is currently self-actualization can be a medium for today's youth. In this study, the author uses Dramaturgy Theory introduced by Erving Goffman 1955 in The Presentation of Self in Everyday Life.                This research methods using qualitative methodology and data collection technique was done by observation, interviews and  study by literature. Trends goes to coffee shop by teen nowdays be assumed as teen’s activity to follow modern life style and it does to complete needs of self actualization.             It was concluded that the phenomenon of teenage habit to go to the coffee shop is an adolescent self-actualization behaviors performed by following a growing trend. Dramaturgy Theory discusses the two sides of teenage life in self actualize, front stage of a teenager is a person who has wide connections and likes to follow the trend of going to the coffee shop, and the back stage of the teenager is the pupil / student in an educational institution and a child in a family whose primary job is to learn and serve the elderly.

  9. Construction products performances and basic requirements for fire safety of facades in energy rehabilitation of buildings

    Directory of Open Access Journals (Sweden)

    Laban Mirjana Đ.

    2015-01-01

    Full Text Available Construction product means any product or kit which is produced and placed on the market for incorporation in a permanent manner in construction works, or parts thereof, and the performance of which has an effect on the performance of the construction works with respect to the basic requirements for construction works. Safety in case of fire and Energy economy and heat retention represent two among seven basic requirements which building has to meet according to contemporary technical rules on planning and construction. Performances of external walls building materials (particularly reaction to fire could significantly affect to fire spread on the façade and other building parts. Therefore, façade shaping and materialization in building renewal process, has to meet the fire safety requirement, as well as the energy requirement. Brief survey of fire protection regulations development in Serbia is presented in the paper. Preventive measures for fire risk reduction in building façade energy renewal are proposed according to contemporary fire safety requirements.

  10. A strategic management model for evaluation of health, safety and environmental performance.

    Science.gov (United States)

    Abbaspour, Majid; Toutounchian, Solmaz; Roayaei, Emad; Nassiri, Parvin

    2012-05-01

    Strategic health, safety, and environmental management system (HSE-MS) involves systematic and cooperative planning in each phase of the lifecycle of a project to ensure that interaction among the industry group, client, contractor, stakeholder, and host community exists with the highest level of health, safety, and environmental standard performances. Therefore, it seems necessary to assess the HSE-MS performance of contractor(s) by a comparative strategic management model with the aim of continuous improvement. The present Strategic Management Model (SMM) has been illustrated by a case study and the results show that the model is a suitable management tool for decision making in a contract environment, especially in oil and gas fields and based on accepted international standards within the framework of management deming cycle. To develop this model, a data bank has been created, which includes the statistical data calculated by converting the HSE performance qualitative data into quantitative values. Based on this fact, the structure of the model has been formed by defining HSE performance indicators according to the HSE-MS model. Therefore, 178 indicators have been selected which have been grouped into four attributes. Model output provides quantitative measures of HSE-MS performance as a percentage of an ideal level with maximum possible score for each attribute. Defining the strengths and weaknesses of the contractor(s) is another capability of this model. On the other hand, this model provides a ranking that could be used as the basis for decision making at the contractors' pre-qualification phase or during the execution of the project.

  11. On the power of autobiographical memories: from threat and challenge appraisals to actual behaviour.

    Science.gov (United States)

    Selimbegović, Leila; Régner, Isabelle; Huguet, Pascal; Chatard, Armand

    2016-11-01

    Autobiographical memories are a major feature of mental life in humans. However, research on the influence of autobiographical recall on actual behaviour is scarce. We predicted and found that general memories of failure and specific memories of success resulted in worse performance than general memories of success and specific memories of failure. This performance pattern was mediated by task appraisal, suggesting that autobiographical memories (of failure and success) impact performance by shaping the perception of the upcoming task. Combined with the fact that these effects occurred even when the content of autobiographical memories was unrelated to the upcoming task, the present research represents an important step forward in understanding how autobiographical recall influences actual behaviour.

  12. Special report. New products that improve officer performance, safety.

    Science.gov (United States)

    1991-12-01

    The need for products that improve performance of security officers is counterbalanced these days by budgetary constraints. While this may limit major investments in security systems and personnel, less costly improvements or innovations might be worth considering. In this report, we will discuss four advances that may be valuable not only in hospital security, but in other industries as well. One of them, a smoke filter, was originally developed for the hotel industry. Another, a drug detection device, may replace the use of undercover agents or drug-sniffing' dogs in certain circumstances. The third new product is an economical patrol vehicle for parking facilities which might replace more costly vehicles such as golf carts or cars. The fourth product, a roving CCTV camera, is actually being tested at a Midwest medical center and may allow you to monitor areas of parking garages with cameras instead of officers on patrol.

  13. Self-employed individuals performing different types of work have different occupational safety and health problems.

    Science.gov (United States)

    Park, Jungsun; Han, Boyoung; Kim, Yangho

    2018-05-22

    We assessed the occupational safety and health (OSH) issues of self-employed individuals in Korea. The working conditions and OSH issues in three groups were analyzed using the Korean Working Conditions Survey of 2014. Among self-employed individuals, "Physical work" was more common among males, whereas "Emotional work" was more common among females. Self-employed individuals performing "Mental work" had more education, higher incomes, and the lowest exposure to physical/chemical and ergonomic hazards in the workplace. In contrast, those performing "Physical work" were older, had less education, lower incomes, greater exposure to physical/chemical and ergonomic hazards in the workplace, and more health problems. Individuals performing "Physical work" were most vulnerable to OSH problems. The self-employed are a heterogeneous group of individuals. We suggest development of specific strategies that focus on workers performing "Physical work" to improve the health and safety of self-employed workers in Korea. © 2018 Wiley Periodicals, Inc.

  14. Safety design guide for safety related systems for CANDU 9

    International Nuclear Information System (INIS)

    Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

    1996-03-01

    In general, two types of safety related systems and structures exist in the nuclear plant; The one is a systems and structures which perform safety functions during the normal operation of the plant, and the other is a systems and structures which perform safety functions to mitigate events caused by failure of the normally operating systems or by naturally occurring phenomena. In this safety design guide, these systems are identified in detail, and the major events for which the safety functions are required and the major safety requirements are identified in the list. As the probabilistic safety assessments are completed during the course of the project, additions or deletions to the list may be justified. 3 tabs. (Author) .new

  15. Safety design guide for safety related systems for CANDU 9

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young [Korea Atomic Energy Research Institute, Daeduk (Korea, Republic of); Wright, A.C.D. [Atomic Energy of Canada Ltd., Toronto (Canada)

    1996-03-01

    In general, two types of safety related systems and structures exist in the nuclear plant; The one is a systems and structures which perform safety functions during the normal operation of the plant, and the other is a systems and structures which perform safety functions to mitigate events caused by failure of the normally operating systems or by naturally occurring phenomena. In this safety design guide, these systems are identified in detail, and the major events for which the safety functions are required and the major safety requirements are identified in the list. As the probabilistic safety assessments are completed during the course of the project, additions or deletions to the list may be justified. 3 tabs. (Author) .new.

  16. Communicating on risk and safety in terms of awareness

    International Nuclear Information System (INIS)

    Hammar, L.; Andersson, Kjell

    1999-01-01

    'Safety awareness' is proposed as a possibly constructive concept for the purpose of promoting initiatives in nuclear safety work and gaining improved understanding when communicating on nuclear safety. Safety is thus conceived as resulting essentially from and actually constituting awareness of critical factors in regard of safety. The concept aims specifically at promoting the view of 'safety' as 'awareness of required conditions for being in control of risk'. It aims as well at making clearer sense in calling for constant improvement of safety, according to practice in a safety culture. This proposed view would be expected to lead to applying the usual types of safety criteria but offers the merit of attracting due attention to 'awareness goals' in process oriented safety management which are fundamental to maintaining and improving safety. Applications are discussed in regard of communicating on nuclear safety between decision-makers and the general public, developing and maintaining safety culture, integrating specialist expert contributions in over-all safety assessment, setting safety goals and using safety indicators

  17. Gas-cooled fast reactor safety

    International Nuclear Information System (INIS)

    Rickard, C.L.; Simon, R.H.; Buttemer, D.R.

    1977-01-01

    Initial conceptual design work on the GCFR began in the USA in the early 1960s and since the later 1960s has proceeded with considerable international cooperation. A 300 MWe GCFR demonstration plant employing three main cooling loops is currently being developed at General Atomic. A major preapplication licensing review of this demonstration plant was initiated in 1971 leading in 1974 to publication of a Safety Evaluation Report by the USAEC Directorate of Licensing. The preapplication review is continuing by addressing areas of concern identified in this report such that a major part of the work necessary to support the actual licensing of a GCFR demonstration plant has been established. The safety performance of the GCFR demonstration plant is based upon its inherent safety characteristics among which are the single phase and chemically inert coolant which is not activated and has a low reactivity worth, the negative core power and temperature reactivity coefficients and the small and negative steam reactivity worth. Recent studies of larger core designs indicate that as the reactor size increases central fuel, clad and coolant reactivity worths decrease and the Doppler coefficient becomes more negative. These inherent safety characteristics are complemented by safety design features such as enclosing the entire primary coolant system within a prestressed concrete pressure vessel (PCRV), providing two independent and diverse shutdown systems and residual heat removal (RHR) systems, limiting the worth of control rods to less than $1, employing pressure-equalized fuel rods, a core supported rigidly at its upper end and otherwise unrestrained and coolant downflow within the core to enhance debris removal should local melting occur. The structurally redundant PCRV design allows the potential depressurization leak area to be controlled and, since the PCRV is located within a containment building, coolant is present even after a depressurization accident and each RHR

  18. Budget and Actuals

    Data.gov (United States)

    Town of Chapel Hill, North Carolina — This dataset contains the Town's Year-to-Date Budget and Actuals for Fiscal Years 2016, 2017, and 2018. Fiscal years run from July 1 to June 30. The data comes from...

  19. Performance indicators at Embalse NPP: PSA and safety system indicators based on PSA models

    International Nuclear Information System (INIS)

    Fornero, D.A.

    2001-01-01

    Several indicators have been implemented at Embalse NPP. The objective was selecting some representative parameters to evaluate the performance of both the plant and the personnel activities, important for safety. A first set of indicators was defined in accordance with plant technical staff criteria. A complementary set of them was addressed later based on WANO guidance. This report presents the set of indicators used at Embalse NPP, centering the description to related to safety systems performance indicators (SSPI). Some considerations are done about the calculation methods, the need for aligning and updating their values following Embalse Probabilistic Safety Assessment (PSA) development, and some pros and cons of using the PSA model for getting systems indicators. Owing to the fact that PSA ownership by utilities is also a subject of the meeting, some characteristics of the organization of the PSA Project are described at the beginning of the report. At Embalse NPP a Level 1 PSA has been developed under the responsibility of its own plant and with an important contribution from the IAEA. PSA was developed at the site, conducting this to a study strongly interactive with the station staff. (author)

  20. 33 CFR 165.1319 - Safety Zone Regulations, Seafair Blue Angels Air Show Performance, Seattle, WA.

    Science.gov (United States)

    2010-07-01

    ... Blue Angels Air Show Performance, Seattle, WA. 165.1319 Section 165.1319 Navigation and Navigable... Thirteenth Coast Guard District § 165.1319 Safety Zone Regulations, Seafair Blue Angels Air Show Performance... Peninsula; thence northerly along the shore of Mercer Island to the point of origin. [Datum: NAD 1983] (c...

  1. Preliminary performance test of control rod position indicator for ballscrew type CEDM

    International Nuclear Information System (INIS)

    Yoo, J. Y.; Kim, J. H.; Hu, H.; Lee, J. S.; Kim, J. I.

    2003-01-01

    The reliability and accuracy of the information on control rod position are very important to the reactor safety and the design of the core protection system. A survey on the RSPT(Reed Switch Position Transmitter) type control rod position indication system and its actual implementation in the exiting nuclear power plants in Korea was performed first. The prototype of control rod position indicator having the high performance for the ballscrew type CEDM was developed on the basis of RSPT technology identified through the survey. The characteristics of control rod position indicator was defined and documented through design procedure and preliminary performance test

  2. FRACTIONAL CRYSTALLIZATION FLOWSHEET TESTS WITH ACTUAL TANK WASTE

    International Nuclear Information System (INIS)

    HERTING, D.L.

    2006-01-01

    Laboratory-scale flowsheet tests of the fractional crystallization process were conducted with actual tank waste samples in a hot cell at the 222-S Laboratory. The process is designed to separate medium-curie liquid waste into a low-curie stream for feeding to supplemental treatment and a high-curie stream for double-shell tank storage. Separations criteria (for Cs-137 sulfate, and sodium) were exceeded in all three of the flowsheet tests that were performed

  3. Improving versus maintaining nuclear safety

    International Nuclear Information System (INIS)

    2002-01-01

    The concept of improving nuclear safety versus maintaining it has been discussed at a number of nuclear regulators meetings in recent years. National reports have indicated that there are philosophical differences between NEA member countries about whether their regulatory approaches require licensees to continuously improve nuclear safety or to continuously maintain it. It has been concluded that, while the actual level of safety achieved in all member countries is probably much the same, this is difficult to prove in a quantitative way. In practice, all regulatory approaches require improvements to be made to correct deficiencies and when otherwise warranted. Based on contributions from members of the NEA Committee on Nuclear Regulatory Activities (CNRA), this publication provides an overview of current nuclear regulatory philosophies and approaches, as well as insights into a selection of public perception issues. This publication's intended audience is primarily nuclear safety regulators, but government authorities, nuclear power plant operators and the general public may also be interested. (author)

  4. Early Performance and Safety of the Micra Transcatheter Pacemaker in Pigs.

    Science.gov (United States)

    Bonner, Matthew; Eggen, Michael; Haddad, Tarek; Sheldon, Todd; Williams, Eric

    2015-11-01

    The Micra® Transcatheter Pacing System (TPS; Medtronic Inc., Minneapolis, MN, USA) is a miniaturized single-chamber pacemaker system that is delivered via catheter through the femoral vein. In this study, the electrical performance was compared between the TPS and a traditional leaded pacemaker. In addition, the safety profile of the two systems was compared by thorough monitoring for a number of adverse events. The TPS was implanted in the right ventricular apex of 10 Yucatan mini pigs and a Medtronic single-lead pacemaker (SLP) was implanted in the right ventricular apex of another 10 pigs and connected to a traditional pacemaker. The electrical performance of all devices was monitored for 12 weeks. The safety profile of each system was characterized using x-ray, computed tomography, ultrasound, blood work, and necropsy to monitor for a variety of adverse events. At implant the mean pacing thresholds were 0.58 ± 0.17 V @0.24 ms and 0.75 ± 0.29 V @0.21 ms for the TPS and the SLP respectively. After 12 weeks, mean thresholds were 0.94 ± 0.46 V and 1.85 ± 0.75 V (P pacemaker system. © 2015 Medtronic PLC. Pacing and Clinical Electrophysiology published by Wiley Periodicals, Inc.

  5. NAVFAC Safety performance and the use of best practices to reduce lost workhours and accidents

    OpenAIRE

    Stone, James Treacy.

    1998-01-01

    CIVINS (Civilian Institutions) Thesis document This thesis analyzes the safety performance of several U.S. Naval Facilities Engineering Command (NAVFAC) projects as they compare to the construction industry as a whole and to the Construction Industry Institute (CII) Member companies. Safety success on a construction project is measured by examining the Lost Workday Case Incident Rate (LWCIR), Recordable Incident Rate (RIR), and the Fatality Incident Rate (FIR). This thesis will endeavor to...

  6. Moderating effect of perceived risk on the relationship between product safety and intention

    Directory of Open Access Journals (Sweden)

    Sarina Ismail

    2015-02-01

    Full Text Available Herbal Products industry has experienced significant growth in product demand. Therefore, this study aims to identify the factors effecting the actual buying of Herbal Product. This study also examines the moderation effect of perceived risk on the relationship between product safety and intention. Mall intercept survey was used to collect data from six various states in Malaysia. The data is analyzed using Partial Least Squares (PLS path modeling. The path coefficient results supported the direct influence of intention on actual buying. Similarly, the findings reveal that perceived risk moderate the relationship between product safety and buying intention.

  7. Designing sustainable concrete on the basis of equivalence performance: assessment criteria for safety

    NARCIS (Netherlands)

    Visser, J.H.M.; Bigaj, A.J.

    2014-01-01

    In order not to hampers innovations, the Dutch National Building Regulations (NBR), allow an alternative approval route for new building materials. It is based on the principles of equivalent performance which states that if the solution proposed can be proven to have the same level of safety,

  8. Performance and Safety Tests on Samsung 18650 Li-ion Cells with Two Capacities

    Science.gov (United States)

    Deng, Yi; Jeevarajan, Judith; Rehm, Raymond; Bragg, Bobby; Zhang, Wenlin

    2001-01-01

    In order to meet the applications for Space Shuttle in the future, Samsung 18650 cylindrical Li-ion cells with two different capacities have been evaluated. The capacities are 1800 mAh, and 2000 mAh. The studies focused on the performance and safety tests of the cells.

  9. Safety Evakuation Of Triga-2000 Reactor Operation Viewed From Safety Culture

    International Nuclear Information System (INIS)

    Karliana, Itjeu

    2001-01-01

    The safety evaluation activities of TRIGA-2000 operation viewed from safety culture performed by questioners data collected from the operators and supervisor site of TRIGA-2000 P3TN, Bandung. There are 9 activity aspects surveyed, for instant to avail the policy of safety from their chairman, safety management, education and training, emergency aids planning, safety consultancy, accident information, safety analysis, safety devices, safety and occupational health. The surveying undertaken by filling the questioner that containing of 9 activity aspects and 20 samples of employees. The safety evaluation results' of the operation personnel in TRIGA-2000 P3TN are good implemented by both the operators and supervisors should be improve and attention need to provide the equipment's. The education and training especially for safety refreshment must be performing

  10. Actual motor performance and self-perceived motor competence in children with attention-deficit hyperactivity disorder compared with healthy siblings and peers.

    Science.gov (United States)

    Fliers, Ellen A; de Hoog, Marieke L A; Franke, Barbara; Faraone, Stephen V; Rommelse, Nanda N J; Buitelaar, Jan K; Nijhuis-van der Sanden, Maria W G

    2010-01-01

    : Children with attention-deficit hyperactivity disorder (ADHD) frequently experience comorbid motor problems, developmental coordination disorder. Also, children with ADHD are said to overestimate their abilities in the cognitive and social domain, the so-called "Positive Illusory Bias." In this cross-sectional study, the relationship between actual motor performance and perceived motor competence was examined. Motor performance was assessed using the Movement Assessment Battery for Children in 100 children and adolescents (age 6-17 years), including 32 children with ADHD combined type, 18 unaffected siblings, and 50 healthy control children. ADHD was diagnosed using Parent and Teacher questionnaires and a clinical interview. Perceived motor competence and interest in the motor domain were rated with the Dutch supplement scale to Harters' Self-Perception Profile for Children, especially focusing on the motor domain (m-CBSK). Children with ADHD had poorer motor performance than unaffected siblings and control children, especially in the field of manual dexterity. However, no relationship was found between motor performance and perceived motor competence. Only children with the very lowest motor performance had a significantly lowered perception of their motor competence. Interest in the motor domain and motor self-perception was positively correlated. Children with ADHD performed poorer on the Movement Assessment Battery for Children, but generally overestimated their own motor competence.

  11. Chronic Conditions, Workplace Safety, And Job Demands Contribute To Absenteeism And Job Performance.

    Science.gov (United States)

    Jinnett, Kimberly; Schwatka, Natalie; Tenney, Liliana; Brockbank, Claire V S; Newman, Lee S

    2017-02-01

    An aging workforce, increased prevalence of chronic health conditions, and the potential for longer working lives have both societal and economic implications. We analyzed the combined impact of workplace safety, employee health, and job demands (work task difficulty) on worker absence and job performance. The study sample consisted of 16,926 employees who participated in a worksite wellness program offered by a workers' compensation insurer to their employers-314 large, midsize, and small businesses in Colorado across multiple industries. We found that both workplace safety and employees' chronic health conditions contributed to absenteeism and job performance, but their impact was influenced by the physical and cognitive difficulty of the job. If employers want to reduce health-related productivity losses, they should take an integrated approach to mitigate job-related injuries, promote employee health, and improve the fit between a worker's duties and abilities. Project HOPE—The People-to-People Health Foundation, Inc.

  12. Westinghouse Hanford Company health and safety performance report. Fourth quarter calendar year 1994

    Energy Technology Data Exchange (ETDEWEB)

    Lansing, K.A.

    1995-03-01

    Detailed information pertaining to As Low As Reasonably Achievable/Contamination Control Improvement Project (ALARA/CCIP) activities are outlined. Improved commitment to the WHC ALARA/CCIP Program was experienced throughout FY 1994. During CY 1994, 17 of 19 sitewide ALARA performance goals were completed on or ahead of schedule. Estimated total exposure by facility for CY 1994 is listed in tables by organization code for each dosimeter frequency. Facilities/areas continue to utilize the capabilities of the RPR tracking system in conjunction with the present site management action-tracking system to manage deficiencies, trend performance, and develop improved preventive efforts. Detailed information pertaining to occupational injuries/illnesses are provided. The Industrial Safety and Hygiene programs are described which have generated several key initiatives that are believed responsible for improved safety performance. A breakdown of CY 1994 occupational injuries/illnesses by type, affected body group, cause, job type, age/gender, and facility is provided. The contributing experience of each WHC division/department in attaining this significant improvement is described along with tables charting specific trends. The Radiological Control Program is on schedule to meet all RL Site Management System milestones and program commitments.

  13. Driver Performance Problems of Intercity Bus Public Transportation Safety in Indonesia

    Science.gov (United States)

    Suraji, A.; Harnen, S.; Wicaksono, A.; Djakfar, L.

    2017-11-01

    The risk of an inter-city bus public accident can be influenced by various factors such as the driver’s performance. Therefore, knowing the various influential factors related to driver’s performance is very necessary as an effort to realize road traffic safety. This study aims to determine the factors that fall on the accident associated with the driver’s performance and make mathematical modeling factors that affect the accident. Methods of data retrieval were obtained from NTSC secondary data. The data was processed by identifying factors that cause the accident. Furthermore data processing and analysis used the PCA method to obtain mathematical modeling of factors influencing the inter-city bus accidents. The results showed that the main factors that cause accidents are health, discipline, and driver competence.

  14. Exposure data and risk indicators for safety performance assessment in Europe.

    Science.gov (United States)

    Papadimitriou, Eleonora; Yannis, George; Bijleveld, Frits; Cardoso, João L

    2013-11-01

    The objective of this paper is the analysis of the state-of-the-art in risk indicators and exposure data for safety performance assessment in Europe, in terms of data availability, collection methodologies and use. More specifically, the concepts of exposure and risk are explored, as well as the theoretical properties of various exposure measures used in road safety research (e.g. vehicle- and person-kilometres of travel, vehicle fleet, road length, driver population, time spent in traffic, etc.). Moreover, the existing methods for collecting disaggregate exposure data for risk estimates at national level are presented and assessed, including survey methods (e.g. travel surveys, traffic counts) and databases (e.g. national registers). A detailed analysis of the availability and quality of existing risk exposure data is also carried out. More specifically, the results of a questionnaire survey in the European countries are presented, with detailed information on exposure measures available, their possible disaggregations (i.e. variables and values), their conformity to standard definitions and the characteristics of their national collection methods. Finally, the potential of international risk comparisons is investigated, mainly through the International Data Files with exposure data (e.g. Eurostat, IRTAD, ECMT, UNECE, IRF, etc.). The results of this review confirm that comparing risk rates at international level may be a complex task, as the availability and quality of exposure estimates in European countries varies significantly. The lack of a common framework for the collection and exploitation of exposure data limits significantly the comparability of the national data. On the other hand, the International Data Files containing exposure data provide useful statistics and estimates in a systematic way and are currently the only sources allowing international comparisons of road safety performance under certain conditions. Copyright © 2013 Elsevier Ltd. All

  15. Nuclear Safety Regulations

    International Nuclear Information System (INIS)

    Novosel, N.; Prah, M.

    2008-01-01

    Beside new Ordinance on the control of nuclear material and special equipment ('Official Gazette' No. 15/08), from 2006 State Office for Nuclear Safety (SONS) adopted Ordinance on performing nuclear activities ('Official Gazette' No. 74/06) and Ordinance on special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety ('Official Gazette' No. 74/06), based on Nuclear Safety Act ('Official Gazette' No. 173/03). The Ordinance on performing nuclear activities regulates the procedure of notification of the intent to perform nuclear activities, submitting the application for the issue of a licence to perform nuclear activities, and the procedure for issuing decisions on granting a licence to perform a nuclear activity. The Ordinance also regulates the content of the forms for notification of the intent to perform nuclear activities, as well as of the application for the issue of a licence to perform the nuclear activity and the method of keeping the register of nuclear activities. According to the Nuclear Safety Act, nuclear activities are the production, processing, use, storage, disposal, transport, import, export, possession or other handling of nuclear material or specified equipment. The Ordinance on special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety regulates these mentioned conditions, whereas compliance is established by a decision passed by the SONS. Special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety are organizational, technical, technological conditions and established system of quality assurance. In 2007, State Office for Nuclear Safety finalized the text of new Ordinance on conditions for nuclear safety and protection with regard to the siting, design, construction, use and decommissioning of a facility in which a nuclear activity is

  16. National Waste Repository Novi Han operational safety analysis report. Safety assessment methodology

    International Nuclear Information System (INIS)

    2003-01-01

    The scope of the safety assessment (SA), presented includes: waste management functions (acceptance, conditioning, storage, disposal), inventory (current and expected in the future), hazards (radiological and non-radiological) and normal and accidental modes. The stages in the development of the SA are: criteria selection, information collection, safety analysis and safety assessment documentation. After the review the facilities functions and the national and international requirements, the criteria for safety level assessment are set. As a result from the 2nd stage actual parameters of the facility, necessary for safety analysis are obtained.The methodology is selected on the base of the comparability of the results with the results of previous safety assessments and existing standards and requirements. The procedure and requirements for scenarios selection are described. A radiological hazard categorisation of the facilities is presented. Qualitative hazards and operability analysis is applied. The resulting list of events are subjected to procedure for prioritization by method of 'criticality analysis', so the estimation of the risk is given for each event. The events that fall into category of risk on the boundary of acceptability or are unacceptable are subjected to the next steps of the analysis. As a result the lists with scenarios for PSA and possible design scenarios are established. PSA logical modeling and quantitative calculations of accident sequences are presented

  17. Considerations on monitoring needs of advanced, passive safety light water reactors for severe accident management

    International Nuclear Information System (INIS)

    Bava, G.; Zambardi, F.

    1992-01-01

    This paper deals with problems concerning information and related instrumentation needs for Accident Management (AM), with special emphasis on Severe Accidents (SA) in the new advanced, passive safety Light Water Reactors (PLWR), presently in a development stage. The passive safety conception adopted in the plants concerned goes parallel with a deeper consideration of SA, that reflects the need of increasing the plant resistance against conditions going beyond traditional ''design basis accidents''. Further, the role of Accident Management (AM) is still emphasized as last step of the defence in depth concept, in spite of the design efforts aimed to reduce human factor importance; as a consequence, the availability of pertinent information on actual plant conditions remains a necessary premise for performing preplanned actions. This information is essential to assess the evolution of the accident scenarios, to monitor the performances of the safety systems, to evaluate the ultimate challenge to the plant safety, and to implement the emergency operating procedures and the emergency plans. Based on these general purposes, the impact of the new conception on the monitoring structure is discussed, furthermore reference is made to the accident monitoring criteria applied in current plants to evaluate the requirements for possible solutions. (orig.)

  18. Safety research colloquium 2013-2014. Vol. 10

    International Nuclear Information System (INIS)

    Pieper, Ralf

    2015-01-01

    Volume 10 of the safety research colloquium 2013-2014 covers the following issues: Design, ergonomics and safety in product development; Germany is searching a final repository site: concepts and status of the final disposal of nuclear waste; collaborating robots - status of research, standardization and validation; psychological workloads - empirical indications; psychological workloads - actual challenges; expert security by occupational health management - challenges to operational practice; expert security by occupational health management - example of a demographic program in the practical realization; challenges in employment legislation - reduction of the key staff; consideration of human factors in hazard assessment a a challenge for every safety engineer, innovative technologies for work equipment and working systems in the context of ambient intelligence and industry 4.0; challenges of functional safety in the automotive sector; nanotechnology - an example for successful technology assessment.

  19. Safety balance: Analysis of safety systems

    International Nuclear Information System (INIS)

    Delage, M.; Giroux, C.

    1990-12-01

    Safety analysis, and particularly analysis of exploitation of NPPs is constantly affected by EDF and by the safety authorities and their methodologies. Periodic safety reports ensure that important issues are not missed on daily basis, that incidents are identified and that relevant actions are undertaken. French safety analysis method consists of three principal steps. First type of safety balance is analyzed at the normal start-up phase for each unit including the final safety report. This enables analysis of behaviour of units ten years after their licensing. Second type is periodic operational safety analysis performed during a few years. Finally, the third step consists of safety analysis of the oldest units with the aim to improve the safety standards. The three steps of safety analysis are described in this presentation in detail with the aim to present the objectives and principles. Examples of most recent exercises are included in order to illustrate the importance of such analyses

  20. Report of a consultants meeting on backfittings and safety enhancement measures in NPPs with WWER 440/213 reactors. Extrabudgetary programme on the safety of WWER NPPS

    International Nuclear Information System (INIS)

    1994-01-01

    The purpose of this Consultants' Meeting held by the IAEA in Vienna from 11-15 April 1994 within the framework of the Extrabudgetary Programme on WWER Safety was to review and analyze safety issues revealed during operation and through analyses of NPPs with WWER 440/213 reactors. The initial list of safety issues based on the available reports from various studies had been prepared by the IAEA secretariat before the meeting, together with indications of safety enhancement measures proposed in various NPP units. During the meeting, the underlying safety concerns and actual technical status of the plants were discussed and the ranking of the safety issues was considered. 58 refs, 1 tab

  1. An empirical analysis of nuclear power plant organization and its effect on safety performance

    International Nuclear Information System (INIS)

    Thurber, J.A.

    1985-01-01

    The paper documents work performed on three tasks. The first task concerned the creation of measures of organizational structure. An earlier review of the literature supported the position that organizational structure (e.g., the way the work of the organization is divided, administered, and coordinated) is a likely determinant of plant safety performance. While data were not available on some salient dimensions of organizational structure, Final Safety Analysis Reports (FSARs), Technical Specifications, and a survey of plant technical resources allowed for measurement on three primary dimensions. These are the vertical structure of the plant (e.g., the number of ranks and the ratio of supervisors to subordinates), the horizontal structure of the plant (e.g., the way the organization is divided into administrative and work units), and the coordinative structure of the plant (e.g., the ways that work units are linked)

  2. Consumer attitudes and the governance of food safety.

    Science.gov (United States)

    Todt, Oliver; Muñoz, Emilio; González, Marta; Ponce, Gloria; Estévez, Betty

    2009-01-01

    This paper reports the analysis of a recent study of public perception of food safety governance in Spain, using genetically modified (GM) foods as an indicator. The data make clear that Spanish food consumers are aware of their rights and role in the marketplace. They are critical of current regulatory decision making, which they perceive to be unduly influenced by certain social actors, such as industry. In contrast, consumers demand decisions to be based primarily on scientific opinion, as well as consumer preferences. They want authorities to facilitate informed purchasing decisions, and favor labeling of GM foods mostly on the grounds of their right to know. However, consumers' actual level of knowledge with respect to food technology and food safety remains low. There are several ambivalences as to the real impact of these attitudes on actual consumer